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CNS Membership ­ Conference Special [For New Members Only] Join now for 2012 and receive remainder of 2011 for only $10! To end of 2011:

Regular member $92.40 [$82.40 + 10] Retired $58.41 [$48.41 + $10]

(HST included!) ______________________________________

Adhésion à la SNC ­ Spécial Conférence [Pour nouveaux membres seulement] Devenez membre pour 2012, et recevez l'adhésion pour le reste de 2011 pour seulement 10$! Jusqu'à fin 2011:

Adhésion standard: 92.40$ (82.40$ + 10$) Retraité: 58.41$ (48.41$ + 10$)

(TVH incluse !) ______________________________________

Organizing Committee / Comité organisateur The CNS recognizes the considerable efforts of the Organizing Committee members named below and of their respective employers in making them available to the CNS for the planning of this conference / La SNC est reconnaissante du travail considérable accompli par les membres du comité organisateur, et remercie également leurs employeurs de leur générosité. Executive Chair / Président exécutif Frank Doyle (CANDU Owners' Group) Hotel, Assistant Executive Chair / Aide-Président exécutif Ben Rouben (12 & 1 Consulting) Treasurer / Trésorier: Ken Smith (UNECAN) Plenary Program Committee / Comité des séances plénières: Murray Stewart (Stewart Advantage Consultants Inc.) Technical Program Co-Chairs / Co-présidents du programme technique: David Novog (McMaster University) John Roberts (CANTECH Associates Ltd.) Student Conference Co-Chairs/ Co-présidents de la conférence étudiante: Emily Corcoran (Royal Military College of Canada) Cherie Ferrari (Kinectrics Inc.) NA-YGN Program/ Programme du Regroupement des jeunes: Christine John (Canadian Affairs Chair/NA-YGN) Chris Waugh (Canadian Regional Lead/NA-YGN) Natalie Sachar (AECL Chapter Lead/NA-YGN) Sponsorship and Exhibitor Committee / Comité des appuis financiers: Eric Williams (Canoe-About Inc.) Richard Moffett (EACL)

Organizing Committee / Comité organisateur

Organizing Committee / Comité organisateur Frank Doyle (CANDU Owners' Group) Anne Greve (AECL Ret.) Honours & Awards Committee Chair / Président du comité des prix et honneurs Krish Krishnan (ADH Technologies) Publicity, Promotions, Communications / Publicité, communications: Jeremy Whitlock (AECL) Fred Boyd (CNS Bulletin) Registration, Conference Administration / Inscriptions, Administration: Denise Rouben (CNS Office/Bureau SNC) Bob O'Sullivan (CNS Office/Bureau SNC) Conference Website / Site web: Elmir Lekovic Signs / Pancartes: Anne Greve (AECL Ret.) Ben Rouben (12 & 1 Consulting) Eric Fowler (Digital Signs & Banners Ltd.) Guest Program / Programme des invité(e)s: Melanie Sachar (AECL) Logo Collection / Rassemblement de logos: Anne Greve (AECL Ret.) Abstract Book / Livret des sommaires: Spot Media CD-ROM Proceedings / Comptes rendus sur cédérom: Spot Media 2012 Conference Executive Chair / Président exécutif de la Conférence 2012 John Roberts (CANTECH Associates Ltd.)

Organizing Committee / Comité organisateur

Conference Summary Schedule / Sommaire de la Conférence Sunday, June 5 / Dimanche 5 juin NA-YGN Professional Development Seminar - Nuclear Knowledge and Leadership Strategy 1 17:00 Registration Opens 14:45 CNS Council Meeting 15:30 CNS Annual General Meeting (Review of CNS Year & Election of CNS Council for 2011-2012) Strategy 3 18:00 - 20:30 Opening Reception Great Room A&B 10:00 - 17:00 Monday June 6 / Lundi 6 juin 07:00 07:00 07:30 08:00 - 09:10 09:30 - 11:45 Speakers & Chairs' of the Day Breakfast Strategy Room 7 Registrants' Continental Breakfast Great Room A & B and Prefunction Guests' Continental Breakfast Strategy Room 5 & 6 Opening Plenary - Minister Brad Duguid Great Room C Plenary I - Review of Energy and Environmental Developments in Relation to the Future of Nuclear Great Room C Monday Luncheon & WB Lewis Lecture Great Room A/B Radiation Applications, Dose and Medical Isotopes Strategy Room 1 Reactor and Radiation Physics 1 Strategy Room 3

Conference Summary Schedule / Sommaire de la Conférence

Conference Summary Schedule / Sommaire de la Conférence Monday June 6 / Lundi 6 juin 14:00 14:00 Thermalhydraulics Strategy Room 5 & 6 Special Session: CANDU Maintenance Conference: Industry Performance ­ Getting a Grip Strategy Room 2 PRA, Human Factors and Reliability Strategy Room 7 Student Poster Session Wine & Cheese Great Room A & B Tuesday June 7 / Mardi 7 juin 07:00 07:00 07:30 08:00 08:00 Speakers & Chairs' of the Day Breakfast Strategy Room 7 Registrants' Continental Breakfast Great Room A & B and Prefunction Guests' Continental Breakfast Strategy Room 5 & 6 Advanced Reactors and Fuel Cycles Fallsview Studio A Plant Life Monitoring, Life Extension, Refurbishment and Aging Fallsview Studio B Materials, Degredation and Issues Fallsview Studio C Fuel, Spent Fuel, Decommissioning and the Environment Strategy Room 2 Reactor Safety and Licensing Strategy Room 3

Conference Summary Schedule / Sommaire de la Conférence

14:00 17:30 - 19:30

08:00 08:00

11:45 14:00

08:00

14:00

Conference Summary Schedule / Sommaire de la Conférence Tuesday June 7 / Mardi 7 juin 11:45 Conference Luncheon and Honours & Awards Ceremony Great Room A & B Keynote Address 65 Years of Nuclear Safety in Canada Great Room C Plenary II - Panel - Communicating the Nuclear Message Great Room C Plenary III - Isotopes and Research Reactors Great Room C Cocktail Reception and Conference Banquet "Elements on The Falls" Restaurant, at the edge of the Falls 14:00 14:00 14:00

Conference Summary Schedule / Sommaire de la Conférence Wednesday June 8, Mercredi 8 juin Process Systems, Measurement, I & C, and Chemistry Strategy Room 1 Reactor and Radiation Physics II Strategy Room 3 Training, Infrastructure, and Communication Fallsview A Special Session: Strategies to Manage Financial and Safety Risk for CANDU 6 Stations for an Extended Life Strategy Room 2 Special Session ­ Fusion Fallsview B Nuclear Technology, Fuel, and Materials Fallsview C

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14:00 14:00

14:00 - 15:40

14:00

16:00 - 17:30

18:30 - 22:00

Wednesday June 8, Mercredi 8 juin 07:00 07:00 07:30 08:00 - 09:45 Speakers & Chairs' of the Day Breakfast Strategy Room 7 Registrants' Continental Breakfast Great Room A & B and Prefunction Guests' Continental Breakfast Strategy Room 5 & 6 Plenary IV - Alternative Energy Technologies Great Room C Plenary V - New Nuclear Technologies Great Room C Wednesday Luncheon Minister Rob Norris Great Room A & B

Conference Summary Schedule / Sommaire de la Conférence Conference Summary Schedule / Sommaire de la Conférence

10:15 - 12:00 12:00

Biography / Biographie

WELCOME TO THE 2011 ANNUAL CONFERENCE OF THE CANADIAN NUCLEAR SOCIETY It is my pleasure, on behalf of the Conference Organizing Committee, to welcome you to the 32nd Annual CNS Conference and the 35th Annual Student Conference of the CNS and the Canadian Nuclear Association. Welcome to all the distinguished and honoured guests who are gathering in Niagara Falls to be `Part of the Energy' where Sir Adam Beck envisioned his dream of `power for the people'. There is no more fitting tribute we can make to his vision than to foster that dream now and into the future. The Committee has organized an excellent venue to help you enjoy, and learn from your experience at, the conference. We are especially honoured to have keynote addresses by the Honourable Ministers representing the energy sectors in the governments of Ontario and Saskatchewan. The North American Young Generation in Nuclear (NAYGN) will conduct a Professional Development Seminar on Sunday June 4. The CNS will hold its Annual General meeting on the same day, followed by the conference reception in which we hope you will meet and mingle with old, and make new, friends. The Plenary and Technical Sessions will commence on Monday followed by the Student Poster session and wine and cheese event. This will give you an opportunity to meet the "future of nuclear" from universities across Canada. You will have the added opportunity to visit the many interesting displays by our conference supporters. The Monday luncheon will feature the W.B. Lewis Lecture, presented by Mr. Bill Pilkington. The Tuesday luncheon will honour the major individual and team contributions to the success of nuclear in Canada and the Tuesday evening banquet will be an event not to be missed. Please check the monitors and signs for the locations of the breakfast gatherings which will be held each morning for speakers and chairs, guests and attendees. I hope that your experience at this year's conference will be rewarding. `Be part of the Energy' and enjoy both the conference and the exciting related venues. Respectfully, Frank Doyle Executive Chair 2011 CNS Conference

Mr. Frank W. Doyle Executive Chair Director of Research & Development CANDU Owners' Group (COG)

Frank Doyle is the Executive Chair of the Canadian Nuclear Society (CNS) 2011 Annual Conference and the incoming CNS President. He is the current 1st Vice President and the Program Chair for the CNS. Frank was appointed Director of the Research and Development Program for CANDU Owners Group (COG) in 2003. Frank graduated with a degree in Mechanical engineering from Nova Scotia Technical College (Dalhousie University) and an MBA from the University of Toronto. His career in the CANDU nuclear industry includes development, engineering, licensing and project management with senior management positions at Atomic Energy of Canada, Ontario Power Generation and CANDU Owners' Group, Inc. He has held engineering management roles for Bruce , Pickering and CANDU 6 Nuclear Power Plants, as well as overall engineering responsibility for returning Darlington and Bruce plants to high power operation. He has worked on the development of CANDU reactor concepts and continues to be an avid proponent for the future of nuclear power. In addition to his continuing interest in the advancement of nuclear power, Frank has served as a member of the board of directors for several non profit organizations and is a member of the Research Advisory Committee for UNENE.

Welcome / Bienvenue

Welcome / Bienvenue

Sunday June 5, Dimanche 5 juin NA-YGN Professional Development Seminar 12:00 - 17:00

Sunday June 5, Dimanche 5 juin NA-YGN Professional Development Seminar 14:00 The People Puzzle ­ Gwen Rousseau, ACR Process Engineering Manager, AECL Mississauga Facilitated by: Mukul Shekhar- AECL Mississauga Chapter Gwen has always been intrigued by `what makes people tick' both in the workplace and in their personal life. This has led her in recent years to become certified as a Human Behaviour consultant. Gwen will be providing you with a glimpse into making sense of the people puzzle through the model of human behaviour and how YOU can use it to enhance YOUR leadership skills. Coffee Break / Pause "MBA versus M.Eng.: What's the Value Proposition?" ­ Panel Discussion with Shehab (Sunny) G. Mustafa, M.Eng. (C'11) P.Eng.; Mayur Upadhyay, MBA (C'10) P.Eng.; Arin Gharakhanian, E.I.T. M.Eng. (C'10) and Zeeshaan Mustafa, MBA (C'12) P.Eng. Facilitated by: Sineaid Lagan, Durham Chapter Have you ever thought about pursuing a Masters degree in Business Administration or Nuclear Engineering? Have you considered how a Masters degree may help in your career development? Are you interested in learning about the challenges and tools needed to balance work, academic and life commitments? The panelists will share their insights and experience as students and recent graduates from the University Network of Excellence in Nuclear Engineering (UNENE) Program and the Rotman School of Management MBA program.

"Nuclear Knowledge and Leadership" The Canadian Nuclear Society (CNS), Cameco and the North American Young Generation in Nuclear (NAYGN) are pleased to invite you to a professional development seminar.

14:45 15:05

12:00

12:05

12:20 13:10

Welcome & Introduction Facilitated by: Christine John ­ NA-YGN Canadian Affairs Chair Chris Waugh ­ NA-YGN Canadian Regional Lead Ice Breaker Facilitated by: Natalie Sachar ­ AECL Chalk River Chapter Get to know your fellow participants as we are led through a fun ice breaker. Lunch and Networking (Sponsored by Cameco) Nuclear FAQs ­ Dr. Jeremy Whitlock, Reactor Physicist, AECL Chalk River Facilitated by: Shaun Saldanha - AMEC NSS Chapter Have you ever wondered how CANDU technology works or about the risks of nuclear technology being used as weapons? Join Dr. Jeremy Whitlock, the author of the website www.nuclearfaq.ca and Reactor Physicist at AECL, as he provides answers to many frequently asked questions.

Sunday / Dimanche

Sunday / Dimanche

Sunday June 5, Dimanche 5 juin NA-YGN Professional Development Seminar 15:50 Sustainable development: A Uranium Mining Perspective ­ Dara Hrytzak-Lieffers, Manager Corporate Social Responsibility, Cameco Corporation Facilitated by: Christine John, NA-YGN Canadian Affairs Chair This presentation will provide an overview of sustainable uranium mining development. From stakeholder engagement, to applying environmental technologies and programs, the discussion will highlight key initiatives for ensuring a sustainable fuel source is developed for the nuclear industry. Introduction to International Youth Nuclear Congress (IYNC) 2012 Facilitated by: Bharath Nangia ­ AMEC NSS Chapter Closing Remarks Facilitated by: Duncan Robinson - NA-YGN President Christine John ­ NA-YGN Canadian Affairs Chair Chris Waugh ­ NA-YGN Canadian Regional Lead 14:45 - 15:30

Sunday June 5, Dimanche 5 juin CNS Council Meeting CNS Council Meeting

Sunday June 5, Dimanche 5 juin CNS Annual General Meeting Strategy Room 3 15:30 - 17:30 Review of CNS Year & Election of CNS Council for 2011-2012

16:35

16:45

Sunday June 5, Dimanche 5 juin Opening Reception Great Room A&B 18:00 - 20:30 Opening Reception

Sunday / Dimanche

Sunday / Dimanche

Biography / Biographie Dr. Adriaan Buijs

Monday June 6, Lundi 6 juin Opening Plenary 8:00 - 9:10 - Great Room C 8:00 Welcoming Remarks and Session Moderator: Adriaan Buijs, Outgoing President, Canadian Nuclear Society Honourary Chair Opening Address: Wayne Robbins, Chief Nuclear Officer, Ontario Power Generation Keynote Address: Hon. Brad Duguid, Minister of Energy, Ontario Special Address: Fukushima Dai-Ichi Nuclear Power Station Update: David Novog Director of the McMaster Institute for Energy Studies NSERC-UNENE Associate Research Chair in Nuclear Safety Analysis Break / Pause

8:05

Adriaan has been with Atomic Energy of Canada Limited from 2001 to 2008, first as senior scientist in safety and licensing in the Reactor Core Physics division, then as section head for neutronic overpower protection in CANDU reactors. In 2006 he became manager of the Physics Design group for the ACR-1000. In January 2009 Adriaan was appointed as professor in the Engineering Physics Department of McMaster University in Hamilton. Adriaan has a Master's degree in experimental physics from the State University in Utrecht. He received a PhD from the same University on work on photon-photon collisions studied at the Stanford Linear Accelerator Center in California, USA. Prior to joining AECL, He was fellow and staff member at CERN, the European Centre for Particle Physics from 1986 to 1994. From 1994 to 2001 he was full professor of experimental physics at Utrecht University and director of the particle physics department. Adriaan has been chairman of the Sheridan Park Branch of CNS from 2004 to 2008, and secretary of the CNS executive from 2004 to 2006. He is currently also treasurer of the Golden Horseshoe Branch of the CNS.

8:15 8:40

9:10

Monday / Lundi

Monday / Lundi

Biography / Biographie

Biography / Biographie Honourable Brad Duguid Minister of Energy, Ontario

Wayne Robbins Chief Nuclear Officer

As Ontario's Minister of Energy, Brad Duguid recently launched Ontario's Long-Term Energy Plan: Building Our Clean Energy Future ­ a comprehensive document outlining how Ontario will meet demand for the next 20 years. This ambitious plan builds on Ontario's commitment to clean energy ­ and the cleaner air, jobs and economic growth associated with it. As Minister of Aboriginal Affairs from 2008 to 2010, Duguid worked at building relationships through agreements with a number of First Nations and Métis organizations, including the transfer of Ipperwash Park to the Kettle and Stoney Point First Nation. He was also instrumental in launching PLAY ­ a program for aboriginal youth to participate in sports and activities such as hockey and learn life skills. Duguid has also served as Minister of Labour and Parliamentary Assistant to the Minister of Municipal Affairs and Housing. Duguid was first elected as the MPP for the riding of Scarborough Centre in 2003. Prior to that, he served on Scarborough and Toronto City Council between 1994 and 2003. Brad continues to live in Scarborough with his wife and two kids.

Wayne Robbins is the Chief Nuclear Officer at Ontario Power Generation (OPG). OPG is an Ontario-based electricity generation company whose principal business is the generation and sale of electricity in Ontario. Wayne Robbins was appointed to this position June 1, 2009. He reports to Tom Mitchell, President & CEO. Prior to this position Wayne was the Senior Vice President, Darlington Nuclear. He reported to the Chief Nuclear Officer and was responsible for the strategic direction, planning and execution required to achieve nuclear production targets at Darlington. September 2005 he was appointed to the position of Deputy Vice President, Darlington Nuclear reporting to the Senior Vice President of Darlington responsible for support organizations and assisting the Senior Vice President in station oversight. Previously, Wayne was the Director of Operations and Maintenance, Pickering B Nuclear. Wayne's experience in operations, maintenance and success in outages was invaluable in meeting the challenges of the extensive outage program for Pickering B. Before his appointment to Pickering B, Wayne held the same position at Pickering A Nuclear. In 2008, Wayne was named OPG's Power Within Leader of the Year and in 2009, was honoured with the Ontario Energy Association leadership award.

Monday / Lundi

Monday / Lundi

Biography / Biographie

David Novog Director of the McMaster Institute for Energy Studies NSERC-UNENE Associate Research Chair in Nuclear Safety Analysis

David Novog is the Director of the McMaster Institute for Energy Studies and the NSERC-UNENE Associate Research Chair in Nuclear Safety Analysis. Dr. Novog obtained his Bachelors degree from the University of Manitoba in Mechanical Engineering and his Ph.D. from McMaster in Nuclear Engineering and is Branch Chair and Member at Large for the CNS. Prof. Novog has been researching and working in the field of nuclear safety for over 15 years. During this time he has been a Senior Analyst or Manager in the field of Nuclear Safety for Mitsubishi Heavy Industries Japan, Ontario Power Generation and Nuclear Safety Solutions. During his career Dr. Novog has contributed in many technical areas. These include international expert reviews with Prof. Apostolakis, current USNRC Commissioner, expert reviews for the Safe Operating Envelope project and reviews of licensing submissions for the Ontario CANDU reactors and NRU. David received an award by the French Embassy to promote scientific and educational exchanges in the area of nuclear engineering. Since joining McMaster in 2006, Dr. Novog has focused on UNENE, NRCAN, IAEA, and Nuclear Energy Agency projects in the areas of nuclear safety and severe accidents. He has given numerous talks to learned societies, media outlets, and the public on the Fukushima accident.

Monday / Lundi

Monday / Lundi

Biography / Biographie

Monday June 6, Lundi 6 juin Plenary I

Dr. Murray J. Stewart President, Stewart Advantage Consultants Inc. Chair, Temporal Power Limited

9:30 - 11:45 - Great Room C "Review of Energy and Environmental Developments in Relation to the Future of Nuclear" The session will give an overview of the nuclear option in light of events in Canada and around the world in the energy and environmental arena. Session Moderator: Murray J. Stewart, President, Stewart Advantage Consultants Inc. 9:30 9:50 The Canadian Energy Framework: Greg Schmidt, President, Energy Council of Canada Advancing Clean Energy Technology in Canada: Geoff Munro, Chief Scientist and Assistant Deputy Minister, Natural Resources Canada The Future of Nuclear Technology: Robert Walker, Senior Vice-President, Nuclear Laboratories, AECL Ontario Electricity Planning: Colin Andersen, President & CEO, Ontario Power Authority Global Nuclear Energy Developments: JeanFrançois Béland, Executive Vice- President, AREVA Canada Newfoundland and Labrador Energy Developments: Gilbert Bennett, Vice-President, Lower Churchill, Nalcor Energy Q & A Period

Dr. Murray J. Stewart founded Stewart Advantage Consultants Inc. in 1993 specializing in strategic and operational planning; marketing; and business assessment primarily in the energy sector. Stewart Advantage is used as the core company to take on long term management and project assignments. Most recently, Dr. Stewart became Chair of Temporal Power Limited. Temporal Power is a developer of electricity storage systems using a proprietary breakthrough flywheel technology. Temporal Power works with electrical utilities to deliver solutions to a range of challenges including integrating renewable power onto the electrical grid. The company is based in Burlington, Ontario. Dr. Stewart was President of the Energy Council of Canada in 2009 and 2010, and was previously in this position from 2004-2006; following which he was the first Executive Director of World Energy Congress - MONTRÉAL 2010. The Energy Council of Canada, one of 93 Member Committees of the World Energy Council, is a vehicle for strategic thinking, networking and action by senior executives in the private and public sectors that have a broad interest in national, continental and global energy issues. Dr. Stewart has held a variety of positions, throughout a career spanning 41 years, in Canadian government and industry. These include research/policy positions with the Government of Canada; Vice President, Canadian General Electric; Chief Executive, James Howden North America; Chair, President & CEO, Canadian Nuclear Association; and President & CEO, ITER Canada. He is a registered Professional Engineer (Mechanical) with a Ph.D. in Metallurgical Engineering from the University of British Columbia; a Member of the Canadian Nuclear Society, Professional Engineers Ontario, and the Ontario Society of Professional Engineers, and a Life Member of the American Society for Metals and the Canadian Institute of Mining and Metallurgy

10:10

10:30 10:50

11:10

11:30

Monday / Lundi

Monday / Lundi

Biography / Biographie

Biography / Biographie Geoff Munro Chief Scientist of Natural Resources Canada & ADM, Innovation and Energy Technology Sector

Gregory B. Schmidt President Energy Council of Canada

Geoff Munro was appointed the Assistant Deputy Minister of Natural Resources Canada's newest sector, the Innovation and Energy Technology Sector (IETS) on April 14, 2009. IETS is comprised of CanmetENERGY, the energy technology R&D arm of the Government of Canada, as well as the Strategic Science & Technology Branch. This appointment is in addition to his June 25, 2007 appointment as Natural Resources Canada's Chief Scientist. In these capacities, Mr. Munro works to position NRCan's science and technology and its energy research and development within the Canadian innovation system and in broader international arenas, as well as lead the implementation of the department's science and technology strategy. Mr. Munro came to Ottawa in December 2004 to take over the responsibilities of Director General of Science and Programs for NRCan's Canadian Forest Service. Prior to that, Mr. Munro was previously the Director General of the Canadian Forest Service ­ Great Lakes Forestry Centre in Sault Ste. Marie, Ontario. Geoff has also worked as a Director of Research and Development for the fish/forestry/wildlife programs for the Ontario Ministry of Natural Resources. Geoff Munro Natural Resources Canada Chief Scientist & Assistant Deputy Minister, Innovation and Energy Technology Sector 580 Booth Street, Ottawa, Ontario Canada K1A 0E4

Mr. Schmidt is President of the Energy Council of Canada joining the Council on August 16, 2010. The Energy council of Canada is the Canadian national member of the World Energy Council and is made up of representatives of all sectors within Canada's energy industry. Mr. Schmidt is responsible for the overall program and management of the Energy Council of Canada, and for support of the World Energy Council as the Canadian Member Secretary. Mr. Schmidt has held a variety of positions, in both the private and public sectors. Prior to joining the Energy Council of Canada he worked with Petro-Canada and the merged Suncor as Senior Director, Government Relations responsible for company's domestic and international government relations program. Among other positions, Mr. Schmidt has served as Chief of Staff to the Deputy Prime Minister of Canada (DPMO); concurrent to the Minister of Natural Resources Canada and of National Revenue and to a different Minister of National Revenue prior to joining the DPMO. A lawyer and an active member of the Law Society of Alberta, Greg spent many years in private practice prior to joining the Government of Canada and prior to joining Petro-Canada. Greg obtained his law degree from the University of Dalhousie. He obtained his Bachelor of Arts degree from the University of Alberta and also attended graduate school at the University of Alberta.

Monday / Lundi

Monday / Lundi

Biography / Biographie

Biography / Biographie

Dr. Robert Walker Senior Vice-President, Nuclear Laboratories

Colin Andersen Chief Executive Officer Ontario Power Authority

Robert Walker was appointed Senior Vice-President, Nuclear Laboratories, of Atomic Energy of Canada Limited (AECL) on November 15, 2010. Dr. Walker has had a distinguished career in the Government of Canada, with more than 25 years experience in science and technology management and 10 years experience in conducting defence research and exploratory development, both at progressively senior levels. Most recently, Dr. Walker was the Assistant Deputy Minister of Science and Technology at the Department of National Defence and the Chief Executive Officer of Defence Research and Development Canada. He currently serves as the elected Chairman of the NATO Research and Technology Board, the senior oversight body for cooperative research and technology within the NATO framework. Dr. Walker earned a B.Sc. in Physics from Acadia University and also holds an M. Eng. in Engineering Physics and a Ph.D. in Electrical Engineering from McMaster University. He is a graduate of the National Defence College and a Fellow of the Canadian Academy of Engineering. Dr. Walker's strong academic credentials, combined with his extensive public policy and laboratory operations experience, make him uniquely suited to build AECL's Nuclear Laboratories into one of the world's foremost nuclear research facilities.

Colin Andersen was appointed Chief Executive Officer of the Ontario Power Authority (OPA) in September 2008. Prior to joining the OPA, Mr. Andersen held a variety of senior financial and policy positions in the Ontario Public Service, playing a lead role in asset management, infrastructure investments and intergovernmental negotiations. Most recently, he was Deputy Minister, Ontario Ministry of Finance; Secretary of Treasury Board; Deputy Minister, Ontario Ministry of Revenue; Chair of the Ontario Financing Authority and Chair of the Ontario Electricity Financial Corporation. Mr. Andersen has a Masters Degree in Economics from the University of Toronto and an Honours Bachelor of Arts from the University of Calgary. The OPA is responsible for ensuring a reliable, long-term supply of electricity for Ontario, focusing on promoting conservation, planning for the long term, and procuring generation resources.

Monday / Lundi

Monday / Lundi

Biography / Biographie

Biography / Biographie

Jean-François Béland Executive Vice President, AREVA Canada Inc.

Gilbert Bennett Vice President, Nalcor Energy Lower Churchill Project

Jean-François Béland is Executive Vice-President at AREVA Canada Inc. He joined AREVA Canada in August 2008 after spending a year at AREVA's global headquarters in Paris. Prior to that time, JeanFrançois worked in the Canadian public service and in the Office of the Prime Minister of Canada, where he served as Policy Advisor on Treasury Board and Governance issues. Jean-François is a graduate of the Université de Montréal (B.Sc.), l'École Nationale d'Administration Publique (graduate diploma in public administration), l'École des Hautes Études Commerciales (graduate diploma in management), Bordeaux Business School (MBA) and l'Université Paris IX Dauphine (M.Sc. Strategic Management). He completed courses towards a Ph.D in Management at l'Université Paris IX Dauphine. Jean-François is a member of the Board of Trustees of the National Gallery of Canada, the Orchestre symphonique de Gatineau and the Investment Committee of the Fondation du CSSS de Gatineau He lives in Gatineau, Québec with his wife and son.

In September 2007, the Government of Newfoundland and Labrador released a provincial Energy Plan which announced the transformation of Newfoundland and Labrador Hydro into a provincial energy corporation. The energy corporation, officially named Nalcor Energy in December 2008, has five lines of business: Newfoundland and Labrador Hydro, Churchill Falls, Lower Churchill Project, Oil and Gas and Bull Arm Fabrication. Nalcor Energy's foundation is built on its base business: the generation and transmission of electrical power. Over the years, the company has expanded into the broader energy sector, including oil and gas, industrial fabrication, wind energy, and research and development. The company is also leading the development of the province's energy resources, including the lower Churchill hydroelectric development. Gilbert Bennett is the Vice President of the Lower Churchill Project. He joined the company in May 2005 and is responsible for the development of the 3,000 MW lower Churchill hydroelectric resource in Labrador ­ one of the best undeveloped hydroelectric sites in North America. Gilbert is a former Vice President of 360networks Canada, and has served in a number of senior engineering and operations roles with GT Group Telecom Services, Cable Atlantic and Newfoundland Telephone/Aliant. Gilbert is a member of the Professional Engineers and Geoscientists of Newfoundland and Labrador. He has a Bachelor of Engineering (Electrical) degree from Memorial University of Newfoundland. Gilbert currently involved with various associations, including Memorial University Board of Regents, Professional Engineers and Geoscientists Newfoundland and Labrador, Energy Council of Canada and the College of the North Atlantic Board of Directors.

Monday / Lundi

Monday / Lundi

Monday June 6, Lundi 6 juin Monday Luncheon & WB Lewis Lecture

Monday June 6, Lundi 6 juin Monday Luncheon & WB Lewis Lecture 11:45 - 14:00 - Great Room A & B

William S. (Bill) Pilkington Senior Vice-President, Operations, AECL Paper Abstract / Sommaire Canada's Nuclear Industry An Operator's Perspective William S. (Bill) Pilkington The evolution of the CANDU Reactor, and continued support for this unique "made in Canada" design has reached an important crossroads. Design options for nuclear new build in Canada must meet utility needs for reliable, low cost base load generation. Will a restructured AECL have the capability to deliver future life extension and new build projects on time and on budget? Will there be a core capability of engineering and R&D support over the life of new and refurbished units? The recent tragedy in Japan will undoubtedly provide new insights on the safety of nuclear generation and is certain to impact decisions on future nuclear investment in Canada...

Bill Pilkington is Senior Vice-President, Operations, with the Commercial Operations division of Atomic Energy of Canada Limited (AECL). Mr. Pilkington leads the Operations team in the delivery of life extension projects and a wide range of nuclear services to customers, as well as preparation for major new build projects. Mr. Pilkington has extensive experience in the Canadian nuclear industry. He began his career with Ontario Hydro at Pickering in 1978, and moved to NB Power for the commissioning of Point Lepreau in 1981. In the years that followed, Mr. Pilkington was certified as Shift Supervisor and progressed through more senior management positions. In 1994, Mr. Pilkington was appointed Point Lepreau Station Manager, a position he held until 2001 when he became Site Director for the facility. As Site Director, Mr. Pilkington played a key role in representing nuclear interests in the restructuring of NB Power in 2004, and in the successful effort to secure a positive decision on the refurbishment of Point Lepreau in July of 2005. Mr. Pilkington joined AECL in 2006 to assist in developing a strong customer focus in CANDU Services. In 2008, he was appointed Senior Vice-President and Chief Nuclear Officer for AECL's Nuclear Laboratories division. In that role, he led the organization through a period of investment to renew infrastructure, improve nuclear waste management and increase overall performance of the Nuclear Laboratories. When the unplanned shutdown of the National Research Universal (NRU) reactor occurred in May 2009, Mr. Pilkington led the team that completed the highly challenging repair and successful Return to Service Project. A native of British Columbia, Mr. Pilkington has a degree in mechanical engineering from the University of Waterloo. He has strong ties to New Brunswick, where he raised his son and daughter, and continues to maintain a residence.

Monday / Lundi

Monday / Lundi

Monday June 6, Lundi 6 juin Radiation Applications, Dose and Medical Isotopes 14:00 - 17:30 - Strategy Room 1 Co-chair: Doug Boreham (McMaster University) 14:00 Aircrew Radiation Exposure Estimates and the Effect of Solar Flare Anisotropy Masashi Takada (International Space Radiation Laboratory) Brent Lewis, Hani Al Anid, Les Bennett (RMC) The Potential Production of molybdenum-99 in CANDU Reactors David R. Novog, Andrew C. Morreale, John C. Luxat (McMaster University) System safety theory and human factors approach to patient safety for radiotherapy Seraphin Chally Abou (U of Minnesota Duluth) Coffee Break / Pause A Predictive Code for International Space Station Radiation Mission Planning Leena Tomi (Canadian Space Agency) Samy El-Jaby, Brent Lewis (RMC) A Novel Neutron-Gamma Dosimeter Tara Wood, Kevin McDermott, Brent Lewis, Emily Corcoran (RMC)

14:30

15:00

15:30 16:00

16:30

Monday / Lundi

Monday / Lundi

Radiation Applications, Dose and Medical Isotopes Paper Abstracts / Sommaires 14:00 -- Strategy Room 1 Aircrew Radiation Exposure Estimates and the Effect of Solar Flare Anisotropy Masashi Takada (International Space Radiation Laboratory) Brent Lewis, Hani Al Anid, Les Bennett (RMC) A transport code analysis using the Monte Carlo N-Particle eXtended code, MCNPX, has been used to propagate an extrapolated particle spectrum based on satellite measurements through the atmosphere to estimate radiation exposure during solar particle events at aircraft altitudes. A comparison was made between the model predictions and actual flight measurements taken with various types of instruments during Ground Level Event 60. A computercode has been developed to implement the model for routine analysis. Current research is focused on introducing a new anisotropy model that uses neutron monitor responses and pitch angle data to identify anisotropy and correct for it.

group of channels can yield 100-115% of the world demand for Mo-99 with minor impacts on standard fuelling operations. While the infrastructure for handling and processing these quantities of material does not currently exist, this paper demonstrates the feasibility of producing large quantities of Mo-99 in a standard CANDU reactor.

[1] CANDU is a trademark of Atomic Energy of Canada.

14:30 -- Strategy Room 1 The Potential Production of MOLYBDENUM 99 in CANDU Reactors David R. Novog, Andrew C. Morreale, John C. Luxat (McMaster University) Technicium-99m is an important isotope utilized worldwide in nuclear medicine. Its parent isotope, Molybdenum-99, is a fission product of U-235 and is produced commercially in a few reactors around the world. The CANDU®[1] reactor with its ability to fuel online and enhanced neutron economy has the potential to produce large quantities of Mo-99. This paper explores production strategies in the low power periphery channels in a generic CANDU reactor. A small

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15:00 -- Strategy Room 1 System safety theory and human factors approach to patient safety for radiotherapy Seraphin Chally Abou (U of Minnesota Duluth) The research questions in this study while developing modern medical technology for safer applications of radiation therapy are ­ what medical and radiobiological effects and their quantitative models must be taken into account while defining the radiation risk. The uncertainty in the expression of these consequences for the delayed effects is one of the important problems the solution of which is necessary for radiation safety. The main principles of ensuring the radiation safety and the assessment of software technological risk developed on the basis of the intrinsic compatibility with safety systems theory, as an example, those which follow the concept of "Inherent safety" are presented in this paper.

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16:00 -- Strategy Room 1 A Predictive Code for International Space Station Radiation Mission Planning Leena Tomi (Canadian Space Agency) Samy El-Jaby, Brent Lewis (RMC) A model developed for radiation mission planning aboard the International Space Station (ISS) is presented. The model utilizes a correlation between the ambient dose equivalent rate determined by a tissue equivalent proportional counter (TEPC) aboard the ISS and the cut-off rigidity parameter estimated from ISS position vectors. A preliminary assessment indicates the model can predict the total ambient dose equivalent to within 20% of tabulated measurements.

Monday June 6, Lundi 6 juin Reactor and Radiation Physics 1 14:00 - 17:30 - Strategy Room 3 Co-chairs: Dorin Nichita (UOIT) Wei Shen (AECL) 14:00 Effects of Structural Materials on BP/CP Uncertainty Studies for RFSP-IST Modelling of WOLSONG CANDU®6 Reactors Dai-Hai Chung, Hyung-Jin Kim (Atomic Creative Technology Co., Ltd.), Sung-Min Kim (KHNP) A Direct Coupling between RFSP and CATHENA Using PVM Eve-Lyne Pelletier, Elisabeth Varin (AECL) Simulation and design of a neutron detector based on Boron-Loaded linear alkyl benzene (LAB) liquid scintillator Ghaouti Bentoumi (École Polytechnique), Xiongxin Dai, Aaron Ho, Guy Jonkmans, Liqian Li (AECL), Guy Marleau (École Polytechnique), Bhaskar Sur (AECL) Coffee Break / Pause Detector System for Radiation Imaging Using Inverse Collimation Arjun Das, Bhaskar Sur, Shuwei Yue, Guy Jonkmans (AECL) Simulation of Adjuster Withdrawal in Darlington Unit 4 Jakub Szymandera, Omar Shaikh, Derek Hennig (AMEC NSS), Steve Goodchild, Constantin Banica (OPG) Comparison of Calculated and Measured FineStructure Reaction Rate Data from CANFLEXRU in ZED-2 Michael Zeller, Julian Atfield (AECL)

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15:00 16:30 -- Strategy Room 1 A Novel Neutron-Gamma Dosimeter Tara Wood, Kevin McDermott, Brent Lewis, Emily Corcoran (RMC) A novel DNA dosimeter, comprised of synthetic DNA strands suspended in water, is capable of accurate absorbed dose-to-tissue measurements in mixed neutron-gamma fields. When exposed to ionizing radiation, the DNA strands break releasing a fluence of visible photons. The system responds equally to all radiation types including neutron radiation. Based on theoretical analysis, the DNA dosimeter is accurate to 14% at one standard deviation when measuring an unknown spectrum of mixed neutron-gamma radiation. Linearity has been experimentally verified in gamma and xray fields from 100 mGy to 10 Gy and the detector's lower limit of detection is 100 mGy.

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Reactor and Radiation Physics 1 Paper Abstracts / Sommaires 14:00 -- Strategy Room 3 Effects of Structural Materials on BP/CP Uncertainty Studies for RFSP-IST Modelling of WOLSONG CANDU®6 Reactors Dai-Hai Chung, Hyung-Jin Kim (Atomic Creative Technology Co., Ltd.) Sung-Min Kim (KHNP) A study has been carried out to gain a picture and some quantitative evaluations of the structural material mesh spacing layout effects of Wolsong CANDU 6 reactors by using the WIMS/DRAGON/RFSP-IST code system. The newly updated code system has been validated to some extents by comparing the Phase-B pre-simulation results of Wolsong Unit 1 against the previously acquired Phase-B commissioning test measurements of Wolsong Units 1,2,3,4. The code validation efforts resulted in the conclusions that the newly adopted code system could be used for the operational support of Wolsong CANDU 6 reactors. As an ongoing striving for the improvement of safe and economic operation of the reactors, a project on BP/CP uncertainty analysis with respect to the WIMS/DRAGON/RFSP-IST code system is planned. The results obtained in the present study strongly suggest that the effects of mesh spacing layouts of structural materials could be used as an important parameter to help grasp a more realistic glance on the overall off-line flux mapping errors that contribute to BP/CP uncertainties.

14:30 -- Strategy Room 3 A Direct Coupling between RFSP and CATHENA Using PVM Eve-Lyne Pelletier, Elisabeth Varin (AECL) An increasing number of safety analyses are being performed with coupled neutronic and thermalhydraulic calculations. Neutronic and thermalhydraulic computer codes, namely RFSP and CATHENA, are currently coupled using scripts. These scripts are used to read and write input files and restart files for both codes, resulting in long computation times. This work presents modifications implemented in RFSP for both the *CERBERUS and *CERBRRS modules, to allow direct coupling with CATHENA using PVM, thus reducing the simulation time. Results obtained with the direct PVMbased coupling are compared to the results produced with scripts for verification purposes. The results are found identical and the simulation time is considerably reduced.

15:00 -- Strategy Room 3 Simulation and design of a neutron detector based on Boron-Loaded linear alkyl benzene (LAB) liquid scintillator Guy Jonkmans, Bhaskar Sur, Xiongxin Dai, Aaron Ho, Liqian Li (AECL) Ghaouti Bentoumi, Guy Marleau (École Polytechnique) A Boron-Loaded linear alkyl benzene (LAB) liquid scintillator (LS) neutron detector has been designed to detect neutrons in high gamma field environment. The detector is made robust by piping the light from a remotely located LS module by an optical fibre. Here we describe a GEANT4 based model to optimize the design of the LS detector. This model includes the physics of neutron interaction with Boron-10, light scintillation by the LAB and light transport in the optical fiber. All the detector components including the scintillator, light guides and an approximation of the

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photomultiplier tube response, are simulated. The results show that for unidirectional beam of thermal neutrons, a small detector with 70 % neutron detection efficiency can be achieved by loading the LAB with 4.5% Boron-10 and by using a 2 meter optical fibre. The simulated output results are compared to actual measurement.

16:00 -- Strategy Room 3 Detector System for Radiation Imaging Using Inverse Collimation Arjun Das, Guy Jonkmans, Shuwei Yue, Bhaskar Sur (AECL) This paper describes the concept of using inverse collimation for directional radiation detection, enabling small, lightweight and cost-effective radiation imaging devices. An inverse collimator has been successfully implemented in a patented detector system that maps the direction and intensities of incident gamma radiation to generate a 4 steradian image of radiation sources. An inverse collimator is presented as a novel solution to heavy and unwieldy collimators, by shielding only from the direction of interest. Applications include visual identification of radiological hazards in nuclear production, waste management, decommissioning, and environments where accessibility is low and risk of radiological contamination is high.

16:30 -- Strategy Room 3 Simulation of Adjuster Withdrawal in Darlington Unit 4 Jakub Szymandera, Omar Shaikh, Derek Hennig (AMEC NSS) Steve Goodchild, Constantin Banica (OPG) Physics simulations in safety analyses are generally performed using a bundle irradiation distribution that is consistent with an approximate time-average configuration. In this paper, three assessments of a spurious adjuster withdrawal event at Darlington are performed with RFSP. The simulations are performed using a time-average irradiation distribution and the SORO predicted irradiation distribution just prior to the actual event. In all three of the assessments it is shown that the results are quite insensitive to the assumed irradiation distribution. This supports the approach of assuming a time-average irradiation distribution in safety analyses.

17:00 -- Strategy Room 3 Comparison of Calculated and Measured Fine-Structure Reaction Rate Data from CANFLEX-RU in ZED-2 Michael Zeller, Julian Atfield (AECL) This paper describes an experiment performed in ZED-2 to provide data appropriate for validating lattice code predictions for qualification of CANFLEX-RU fuel in CANDU®. The experiment involved the measurement of fine-structure reaction rates in a CANFLEX-RU demountable bundle. Experimental results are compared to calculations using the lattice code WIMS-IST.

CANDU® is a registered trademark of Atomic Energy of Canada Limited (AECL).

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Monday June 6, Lundi 6 juin Thermalhydraulics 14:00 - 17:30 - Strategy Room 5 & 6 Co-chairs: Glenn Harvel (UOIT) Laurence Leung (AECL) 14:00 Severe Accident Analysis of Shutdown State Accident Using MAAP4-CANDU to Support Level 2 PSA for the POINT LEPREAU Station Refurbishment Project Sergei Petoukhov, Morgan Brown, Mani Mathew (AECL) Qinshan CANDU®6 Main Heat Transport System High Accuracy Performance Tracking in Support of Regional Overpower Protection Wolfgang Hartmann (AECL), Chun Zeng, Xiaochan Mou (TQNPC) IAEA ICSP on Evaluation of System Codes for HWR SBLOCA Jong Ho Choi (IAEA), Matt Krause (AECL) Coffee Break / Pause Severe Accident Analysis of Stagnation Feeder Break Scenarios Using MAAP4-CANDU for Application to the Level 2 PSA for the POINT LEPREAU Station Refurbishment Project Sergei Petoukhov (AECL), Ghulam Khawaja (OPG) Bearing Pad to Pressure Tube Contact Simulation Farshad Talebi, Azin Behdadi (PhD Student), John C. Luxat (McMaster University) Minor Design Changes for Controlling Reactor Inlet Header Temperatures in CANDU Reactors Emma Yang, James Sherin, Vinod Chugh (AMEC NSS)

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Thermalhydraulics Paper Abstracts / Sommaires 14:00 -- Strategy Room 5 & 6 Severe Accident Analysis of Shutdown State Accident Using MAAP4-CANDU to Support Level 2 PSA for the POINT LEPREAU Station Refurbishment Project Sergei Petoukhov, Mani Mathew, Morgan Brown (AECL) A Level 2 Probabilistic Safety Assessment was performed for the Point Lepreau Generating Station. The MAAP4CANDU code was used to calculate the progression of postulated severe core damage accidents and fission product releases. Five representative severe core damage accidents were selected: Station Blackout, Small Loss-ofCoolant Accident, Stagnation Feeder Break, Steam Generator Tube Rupture, and Shutdown State Accident. Analysis results for the reference Shutdown State Accident scenario are discussed in this paper.

association with an optimized parameter tracking and adjustment methodology, confirm continued safe reactor operation. This paper demonstrates that Qinshan CANDU Unit 1, as compared to other CANDU 6 nuclear reactors of earlier design, continues to exhibit significantly improved performance with much reduced plant aging effects. This paper further demonstrates the high accuracy of the advanced performance tracking and adjustment methodology and applies it to Qinshan CANDU Unit 1, ensuring and demonstrating the continued excellent performance of the reference analytic models. The analytic methodology as well as the advanced performance tracking and analysis methodology can also beneficially be applied to both new and refurbished CANDU type nuclear reactors.

14:30 -- Strategy Room 5 & 6 Qinshan CANDU®6 Main Heat Transport System High Accuracy Performance Tracking in Support of Regional Overpower Protection Wolfgang Hartmann (AECL) Xiaochan Mou, Chun Zeng (TQNPC) This paper deals with the Qinshan CANDU® 6 main Heat Transport System (HTS) high accuracy performance tracking/adjustment up to about 7 years of operation in support of Regional Overpower Protection (ROP). Operational and aging related changes of the HTS throughout its lifetime may lead to restrictions in certain safety system settings and hence some restriction in performance under certain conditions. A step in confirming safe reactor operation is the tracking of relevant data and their corresponding interpretation by the use of appropriate thermalhydraulic analytic models. Analytic predictions, in

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15:00 -- Strategy Room 5 & 6 IAEA ICSP on Evaluation of System Codes for HWR SBLOCA Matt Krause (AECL) Jong Ho Choi (IAEA) Activities within the frame of the IAEA's Technical Working Group on Advanced Technologies for HWRs (TWG-HWR) are conducted in a project within the IAEA's sub- program on nuclear power reactor technology development. One of the activities recommended by the TWG-HWR was an international collaborative standard problem (ICSP) entitled "Comparison of HWR thermal-hydraulic code predictions with SBLOCA experimental data". Its main objective is to enhance the confidence in the predictions made by computer codes used in different countries for thermal-hydraulics safety analyses through their inter-comparison and validation. Two RD-14M Small Break Loss Of Coolant Accident (SBLOCA) tests, simulating HWR LOCA behavior, that were conducted by Atomic Energy of Canada Ltd (AECL) were selected for this ICSP project. This paper provides some results and lessons learned from the ICSP.

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16:00 -- Strategy Room 5 & 6 Severe Accident Analysis of Stagnation Feeder Break Scenarios Using MAAP4-CANDU for Application to the Level 2 PSA for the POINT LEPREAU Station Refurbishment Project Sergei Petoukhov (AECL) Ghulam Khawaja (OPG) A Level 2 Probabilistic Safety Assessment was performed for the Point Lepreau Generating Station. The MAAP4CANDU code was used in this study to calculate the progression of postulated severe core damage accidents and fission product releases. Five representative severe core damage accidents were selected for this assessment: Station Blackout, Small Loss-of-Coolant Accident, Stagnation Feeder Break, Steam Generator Tube Rupture, and Shutdown State Accident. Analysis results for the reference Stagnation Feeder Break scenario are discussed in this paper. The major findings of this study are that the calandria vessel did not fail, containment did not fail, and therefore the release of fission products to the environment during this scenario is predicted to be very low.

paper is to eval- uate the local thermal-mechanical deformation of a pressure tube in a CANDU reactor and to investigate the fuel channel integrity under localized contact between bearing pad and pressure tube. Furthermore, the mechanistic models are validated against the experimental works per- formed at WRL (Whiteshell research laboratory). Calculations are performed using the finite element method in which the heat, thermal mechanical and creep strain equations are solved, simultaneously. According to the experimental set up, the heat conduction from bearing pads to the inner surface of the pressure tube with appropriate convective and radiation boundary condi- tions has been simulated. Furthermore, the thermal creep strain deformation has been obtained for when the pressure tube is still under operational condition. It is observed that the pressure tube thermal strain will occur if sufficient high temperature is reached however, depending on the severity of flow degradation in the fuel channel, these localized hot spots could represent a potential creep strain failure of the pressure tube. Whether the pressure tube would fail at these hot spots before contacting the calandria tube depends on the localized temperature and expe- rienced pressure transients. Sensitivity analysis is performed in order to evaluate the contact conductance, the contact width and zircaloy surface emissivity. The pressure tube local strain is very sensitive to these parameters.

16:30 -- Strategy Room 5 & 6 Bearing Pad to Pressure Tube Contact Simulation John C. Luxat (McMaster University) Azin Behdadi, Farshad Talebi (PhD Student) Thermal creep strain deformation is a very important pressure tube failure mechanism. During a postulated LOCA (loss of coolant accident) with failure of emergency core injection sys- tem (ECIS), the fuel cladding temperature rapidly increases and the pressure tube becomes completely dry in a few seconds after flow stagnation occurs. Subsequently, the pressure tube circumference is heated by thermal radiation except at the spots where the bearing pads are in direct contact with the pressure tube. Therefore, the localized hot spots are developed on the pressure tube's inner surface under the bearing pads. The main objective of this

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17:00 -- Strategy Room 5 & 6 Minor Design Changes for Controlling Reactor Inlet Header Temperatures in CANDU Reactors Emma Yang, James Sherin, Vinod Chugh (AMEC NSS) Most CANDU operators are dealing with increasing Reactor Inlet Header (RIH) Temperatures. Expensive Steam Generator (SG) tube cleaning campaigns have been executed on a number of units with varying degrees of success. Other operators have resorted to boiler pressure reductions, which in some cases is leading to unit deratings and lost production. Several minor design changes were evaluated as an alternative means for controlling RIH temperature. The general conclusion of the study is that in the right circumstances, minor design changes can provide a cost effective means of controlling RIH temperatures by avoiding or deferring repeated Inner Diameter (ID) SG tube cleanings and/or additional power deratings.

Monday June 6, Lundi 6 juin Special Session: CANDU Maintenance 14:00 - 17:30 - Strategy Room 2 Industry Performance - Getting a Grip Co-chairs: Neil Mitchell (Ontario Power Generation Darlington Refurbishment) Jacques Plourde (J.A. Plourde Performance Ltd.) Paper A - CMC 2011 Conference-Focus Overview Neil Mitchell (OPG), Jacques Plourde (J.A. Plourde Performance Ltd.) 15:00 Paper B - The Outage Cycle Continuum Jacques Plourde (J.A. Plourde Performance Ltd.) 15:30 Coffee Break / Pause 15:50 Paper C - The Configuration Management Challenge James Smith (Consultant to SNC-Lavalin) 16:15 Paper D - Service-Provider and Utility TaskLeadership Integration Sean Bagshaw (AP Services Inc.) 16:40 Paper E - Operating Chemistry, Its Effects, and Its Optimization Bill Schneider (CMC2011 Exec Chair) 17:05 Paper F - Intelligent Replication - a Way-ofWorking for the Future Bill Schneider (CMC2011 Exec Chair) CMC 2011 Messaging...each of the Special-Session Papers, and as many as possible of the CMC conference papers, is intended to convey our three-part messaging as noted in Items i), ii), iii) below; i) one part "high-level utility-executive statement" 14:00

ii) one part "why is this so important" [aka the `importance shake-down'] iii) one part "thoughtful discussion" [aka `Service-Provider tutorial']

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Monday June 6, Lundi 6 juin Special Session: CANDU Maintenance "... if we look critically at our-selves we may see that the lagging of the nuclear new-build programs is perhaps, due more to weak industry performance and less-than-stellar engineering rigor, particularly at the front end of our programs, than to the consequences of any event or to interventions by our industry's `detractors'. CMC011, by tackling the ways-of-working issues which underlie the above-mentioned performance deficit chooses instead to promote such ways-of-working improvements as an essential element in re-establishing the public and governmental confidence-base as is so necessary for progress" Special Session: CANDU Maintenance Conference: Industry Performance ­ Getting a Grip Paper Abstracts / Sommaires 14:00 -- Strategy Room 2 Paper A - CMC 2011 Conference-Focus Overview Neil Mitchell (OPG) Jacques Plourde (J.A. Plourde Performance Ltd.) `Predictability' [definition ­ `Dependable Outcomes Based on Pre-Verified Plans and Processes'] - is key to nuclear industry public and stakeholder confidence ­ predictability in public, employee, and environmental safety; in reliable production; in improvement and refurbishment project execution; and in overall financial performance. CMC 2011 addresses this by focusing on; Utility experience with optimally-managed outages in well-run plants, on the ways-of-working processes, tools and behaviors required by the industry to succeed; applying lessons-learned to hugely-complex and scopeexpansion prone projects like refurbishments ­ and eventually new-build. Configuration management, operating chemistry, Utility/Service-Provider interfaces, and intelligent replication are explored along the way.

15:00 -- Strategy Room 2 Paper B - The Outage Cycle Continuum Jacques Plourde (J.A. Plourde Performance Ltd.) Operating-cycle or outage-cycle focus - in well-run plants, the two exist as a continuum, and the plant's operating success and reliability depend on that. Both concern selecting the right work for execution at the right time, and maximizing completion. Both involve intensely-integrated utility/ service-provider task planning and execution, plus rigorous management oversight throughout. Opportunities abound: service providers can perform work `in-operation' as well as during outages; also longer operating intervals with shorter planned outages are a possibility. Two examples are presented to illustrate this continuum: a new outage scope selection approach, and industry experience with maintenance backlogs.

15:50 -- Strategy Room 2 Paper C - The Configuration Management Challenge James Smith (Consultant to SNC-Lavalin) Configuration Management is the process of ensuring the construction, operation, maintenance and testing of the systems, components and structures of a physical plant are in full compliance with the design requirements. It also warrants that all documentation detailing the physical plant is consistent with what actually exists, and is readily retrievable. A rigorous Configuration Management system supports making safe, knowledgeable and cost effective decisions with confidence. This paper addresses Configuration Management at the three levels of: "Utility Executive Level statement of need", "...a why is this so important anyway discussion", and as a "thoughtful tutorial" on its features and practice.

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16:15 -- Strategy Room 2 Paper D - Service-Provider and Utility Task-Leadership Integration Sean Bagshaw (AP Services Inc.) As nuclear power utilities strive to stream-line their organizations, while improving outage and refurbishment project performance, the necessity for effective relationships and interaction between utility and service-providers becomes paramount. Successful integration of ServiceProvider into the Utility's environment is achievable and has been demonstrated. Early and extensive engagement in front-end planning, single-point-of-continuity, and the use of integrated execution teams, are some of the critical elements for ensuring success. The paper discusses Task-Leadership Integration at the three levels of; utility executive level `need-statement'; a `why is this important' discussion; and as a `thoughtful tutorial' on its features and practice.

17:05 -- Strategy Room 2 Paper F - Intelligent Replication - a Way-of-Working for the Future Bill Schneider (CMC2011 Exec Chair) `Intelligent Replication' - a way-of-working which is essential for proven-performance based success for future refurb, maintenance, and new-builds. `Rigorous Replication' ­ for the capture within a `baseprogram' of what is `proven' ­ supplemented by a sidestream of `Intelligent, OpEx-Driven, Issue-Resolution' ­ for addressing off-line, of the hopefully short list of issues which may persist - and the controlled introduction of such corrections to the base-program as/ if appropriate. The paper discusses Intelligent Replication at the three levels of; utility `need'; `importance'; and as a `thoughtful tutorial'.

16:40 -- Strategy Room 2 Paper E - Operating Chemistry, Its Effects, and Its Optimization Bill Schneider (CMC2011 Exec Chair) "... a gut-level understanding of basic boiler-cycle chemistry parameters by those on the front-lines of operations and maintenance is fundamental to achieving reliable, highavailability plant performance" ­ Ref Author 1. To that end, this paper presents Plant Operating Chemistry in exactly the reverse order to the norm. By starting with steamcycle corrosion product transport ­ chemistry is not only dead simple, but related directly to the experience and OpEx observations of service-providers everywhere. Such insight ultimately leads to interest in the more-aggressive boilercycle species, primary circuit conditions, etc. ­ all highly preferable to the `clouding-over-of-faces' upon mere mention of the `c' word.

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Monday June 6, Lundi 6 juin PRA, Human Factors and Reliability 14:00 - 17:30 - Strategy Room 7 Co-chairs: Angela Vieira (AMEC NSS) Mahesh Pandey (University of Waterloo) 14:00 Generation Risk Assessment of Main Output Transformers Mikko Jyrkama, Mahesh Pandey (U of Waterloo) GRA Model Development at Bruce Power Ranbir Parmar, Khai Ngo (AMEC NSS), Ian Cruchley (Bruce Power) Determination of Large Early Release Frequency Used in PSA Kyungmin Kang (KINS), Moosung Jae (Hanyang University) Coffee Break / Pause Implementation of CNSC Regulatory Guide G323 at Pickering Nuclear Generating Station Louie Shoukas (OPG), Angela Vieira, Jessica Phyland (AMEC NSS) AREVA Fatigue Concept: FAMOS for CANDU and its accompanying fatigue assessment methods, great value for availability and LTO in NPPs Christian Poeckl, Benedikt Heinz (AREVA NP GmbH) Risk-Informed Prediction of Feeder End of Life Mikko Jyrkama, Mahesh Pandey (U of Waterloo)

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PRA, Human Factors and Reliability Paper Abstracts / Sommaires 14:00 -- Strategy Room 7 Generation Risk Assessment of Main Output Transformers Mikko Jyrkama, Mahesh Pandey (U of Waterloo) The loss of large power transformers may have major implications for plant operation, performance, safety, and economics. This paper examines the generation risk associated with main output transformers (MOTs) at a large nuclear station using the Monte Carlo simulation approach. The developed methodology is used for spare inventory optimization and making transformer replacement projections, while taking into account the specific demographics and condition of the transformer population. The transformer reliability is described using a flexible, three parameter mixed Expontial/Weibull lifetime distribution. The results of the study indicate that, due to the long procurement time for large transformers, at least 1 or 2 spare transformers are needed immediately to minimize the risk to the station. Delaying the investment, even for a single year, would increase the risk significantly.

present the scope of the GRA model development project, methodology employed, and the results and path forward for the model implementation at Bruce Power. The required work was split into three phases. Phase 1 involved development of GRA models for the twelve systems most important to electricity production. Ten systems were added to the model during each of the next two phases. The GRA model development process consists of developing system Failure Modes and Effects Analyses (FMEA) to identify the components critical to the plant reliability and determine their impact on electricity production. The FMEAs were then used to develop the logic for system fault tree (FT) GRA models. The models were solved and post-processed to provide model outputs to the plant staff in a user-friendly format. The outputs consisted of the ranking of components based on their production impact expressed in terms of lost megawatt hours (LMWH). Another key model output was the estimation of the predicted Forced Loss Rate (FLR).

14:30 -- Strategy Room 7 GRA Model Development at Bruce Power Ranbir Parmar, Khai Ngo (AMEC NSS) Ian Cruchley (Bruce Power) n 2007, Bruce Power undertook a project, in partnership with AMEC NSS Limited, to develop a Generation Risk Assessment (GRA) model for its Bruce B Nuclear Generating Station. The model is intended to be used as a decision-making tool in support of plant operations. Bruce Power has recognized the strategic importance of GRA in the plant decision-making process and is currently implementing a pilot GRA application. The objective of this paper is to

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15:00 -- Strategy Room 7 Determination of Large Early Release Frequency Used in PSA Kyungmin Kang (KINS) Moosung Jae (Hanyang University) The correlations between Large Early Release Frequency (LERF) and Early Fatality need to be investigated for riskinformed application and regulation. In RG-1.174, there are decision-making criteria using the measures of CDF and LERF, while there are no specific criteria on LERF. Since there are both huge uncertainty and large cost need in off-site consequence calculation, a LERF assessment methodology need to be developed and its correlation factor needs to be identified for risk-informed decision-making. This regards, the robust method for estimating off-site consequence has been performed for assessing health effects caused by radioisotopes released from severe accidents of nuclear

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power plants. And also, MACCS2 code are used for validating source term quantitatively regarding health effects depending on release characteristics of radioisotopes during severe accidents has been performed. This study developed a method for identifying correlations between LERF and Early Fatality and validates the results of the model using MACCS2 code. The results of this study may contribute to defining LERF and finding a measure for risk-informed regulations and risk-informed decision-making.

16:00 -- Strategy Room 7 Implementation of CNSC Regulatory Guide G-323 at Pickering Nuclear Generating Station Louie Shoukas (OPG) Angela Vieira, Jessica Phyland (AMEC NSS) The Minimum Staff Complement (MSC) is the minimum number of people required to be present on a given shift to ensure safe and reliable operation of the nuclear facility, while maintaining an adequate preparedness level in handling all possible emergency scenarios. In 2009-2010, Ontario Power Generation (OPG) examined its MSC at Pickering using the newly issued regulatory guidelines specified in CNSC Guide G323 `Ensuring the Presence of Sufficient Qualified Staff at Class I Nuclear Facilities ­ Minimum Staff Complement'. This was the first project of this nature in the Canadian Nuclear industry to be executed using G-323. The following paper provides an overview of the methodology that was developed to demonstrate Pickering's alignment with G-323 in addition to the successes and challenges of the project.

16:30 -- Strategy Room 7 AREVA Fatigue Concept: FAMOS for CANDU and its accompanying fatigue assessment methods, great value for availability and LTO in NPPs Christian Poeckl, Benedikt Heinz (AREVA NP GmbH) A crucial issue in the view of changing boundary conditions is the prevention of fatigue damages: code modifications, lifetime extension and new plants with operating periods of 60 years. `The AREVA fatigue concept (AFC) provides for a multiple step and multidisciplinary process (process engineering, fatigue monitoring, fatigue analyses, etc.)against fatigue before and during the entire operation of nuclear power plants' (Rudolph 2009). Within this integral concept AREVA's fatigue monitoring system FAMOS serves as the basis. With the help of FAMOS the real local operating loads are measured at the fatigue relevant locations of the primary and secondary circuit pressure boundary components. FAMOS for CANDU and its accompanying fatigue assessment methods: great value to availability, optimisation and long term operation LTO.

17:00 -- Strategy Room 7 Risk-Informed Prediction of Feeder End of Life Mikko Jyrkama, Mahesh Pandey (U of Waterloo) The operating life of feeder piping is negatively impacted by flow accelerated corrosion (FAC). In this study, an assessment of a large set of inspection data reveals that FAC in feeders is a relatively stationary process, with variability only at the local scale. Given the added uncertainty from inspection coverage, a new method for estimating the thinning rate and feeder EOL is developed using a probabilistic approach. The results of the study illustrate the benefits of the methodology in supporting risk-informed decision making at the station by quantifying the present and incremental risk in the feeder system over time.

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Monday June 6, Lundi 6 juin Student Poster Session and Wine & Cheese 17:30 - 19:30 - Great Room A & B Kinetics of passive film growth on Alloy 800 in the presence of hydrogen peroxide Tirdad Nickchi and Akram Alfantazi Department of materials science and engineering, the University of British Columbia, Vancouver, B.C., Canada The Influence of Platinum Coating on Hydrogen Diffusion through Carbon Steel Chutima Kongvarhodom, Frank Steward and Derek Lister Chemical Engineering, University of New Brunswick Centre for Nuclear Energy Research, University of New Brunswick An ab initio study of hydrated cobalt(II) hydroxy complexes Daniel Whynot and Cory Pye Saint Mary's University Large Scale Measurement of Critical Heat Flux on a Downward Facing Brass Plate in a Pool Boiling Environment Marko Gocmanac McMaster University The Influence of Radiation Exposure and Hydrogen Peroxide on the Corrosion Behaviour of Cobalt and Stellite-6 Mehran Behazin, Xueyuan Zhang, Jamie Noël and Clara Jungsook Wren University of Western Ontario Association of LiOH in supercritical water and pH control at SCWR operating conditions Ruth A. Carvajal-Ortiz, Andriy Plugatyr and Igor M. Svishchev Chemistry Department - Graduate Student

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The Phase Transport and Reactions of -Irradiated Aqueous-Ionic Liquids Susan Howett, Jiju Joseph, James Noël and J. Clara Wren UWO A Predictive Code for International Space Station Radiation Mission Planning Samy El-Jaby, Brent Lewis and Leena Tomi Royal Military College of Canada Canadian Space Agency Effect of Dissolved Chromium on Water radiolysis Product Behaviour and formation of Chromium oxide nanoparticles by Gamma radiolysis Leena Alrehaily, Jiju Joseph and J.Clara Wren University of Westren Ontario Marginal and Joint Distribution for Spectral Accelerations on Uniform Hazard Spectra De-Yi Zhang, Shun-Hao Ni, Wei-Chau Xie and Mahesh D. Pandey PhD, University of Waterloo Professor, University of Waterloo A review of potential spent nuclear fuel alteration phases occurring under oxidizing and reducing conditions Yannick Beauregard and David W. Shoesmith University of Western Ontario Modelling RD14-M Header Conditions: Coupling of STAR-CCM+ and CATHENA Paul Szymanski McMaster University Numerical Simulation of Laminar Pulsations in Subchannel Geometries Alan Chettle, Marilyn Lightstone and Stephen Tullis McMaster University Development of a Mathematical Model of the Non Intrusive Ultrasonic Cross Correlation Flow Meter Alexander Gurevich De Montfort University, UK

A Novel Neutron-Gamma Dosimeter Tara Wood, Brent Lewis, Emily Corcoran and Kevin McDermott Royal Military College of Canada Tri-Directional Spectrum-Compatible Earthquake TimeHistories For Nuclear Energy Facilities Shun-Hao Ni, Wei-Chau Xie and Mahesh D. Pandey University of Waterloo Modeling a ZED-2 (Th,Pu)O2 Fuel Bundle Experiment Using DRAGON and DONJON Shahab Dabiran and Adriaan Buijs McMaster University An Ab Initio Study of Hydrated Cobalt(II) and Complexation with Chloride Daniel C. M. Whynot, Jane P. Ferguson and Cory C. Pye Saint Mary's University Probabilistic Assessment of SG Tubing Integrity Considering Parametric Uncertainties Dongliang Lu, Mahesh D. Pandey and Wei-Chau Xie University of Waterloo Deposition of Magnetite Particles in a CANDU Supercritical Water Reactor Keigo Karakama, Steve Rogak and Akram Alfantazi University of British Columbia An In-situ Raman Study of Electrochemically Active Lithium Ferrite Maggie Manley and William Cook UNB - PhD Student UNB - Associate Professor Indications of SCC Resistance in an Alloy 82 Dissimilar Metal Weld in a Simulated Primary Water Environment Suraj Persaud, Roger Newman and Sridhar Ramamurthy University of Toronto, Ontario, Canada University of Western Ontario, London, Ontario, Canada

Monday / Lundi

Monday / Lundi

MODELLING AND ANALYSIS OF (Th,Pu)O2 FUEL IN A CANDU6 REACTOR Russell Truesdell Author An Examination of the Time-Dependent Background Counts of the Delayed Neutron Counting System at the Royal Military College of Canada Madison Sellers, Emily Corcoran and David Kelly Royal Military College of Canada Reviewing the Environmental Statutes of Canadian Nuclear Regulations and their Impact on the GenerationIV Reactor Ima Ituen McMaster University Design of a Test Facility for the Study of Nanofluid Pool Boiling James Strack McMaster University AIRCREW RADIATION EXPOSURE ESTIMATES AND THE EFFECT OF SOLAR FLARE ANISOTROPY Hani Al Anid, Brent Lewis, Les Bennett and Masashi Takada Author Supervisor Co-Author Model Support for an Out-Reactor-InstrumentedDefected-Fuel-Experiment to Validate the RMC Fuel Oxidation Model Aaron Quastel, Emily Corcoran, Brent Lewis, Cathy Thiriet and Gordon Hadaller Royal Military College of Canada AECL - Chalk River Laboratories Stern Laboratories Inc. Review on the Effect of H2O2 on Dissolution of Spent Fuel (UO2) Linda Wu and David W. Shoesmith UWO

Safety Verification in Process Industries using Quantitative Assessment of Hazard Magnitude (QAHM) Methodology Achint Rastogi and Hossam A. Gabbar Graduate Student, UOIT Associate Professor, UOIT Chemistry of High Density Slag Concrete and Corrosion Resistance of Embedded Steels Parthiban Nadarajah and Roger Newman University of Toronto Neutron Activation for Planar and SPECT Imaging: Feasibility of Locating Metastatic Bone Lesions in the Axial Skeleton Adam Bell, Glenn McRae, Glenn Wells and Richard Wassenaar Carleton University Cardiac Imaging, University of Ottawa Heart Institute Division of Nuclear Medicine, The Ottawa Hospital Characterization of Film Properties on Ni-Cr-Mo Alloys Xiangrong Zhang and David W. Shoesmith The University of Western Ontario Analysis of Existing and New Heat Transfer Correlations for Super Critical Water Flowing in Vertical Bare Tubes Sahil Gupta, Sarah Mokry and Igor Pioro UOIT Kinetics of the Reaction Between Mu and Ni2+ in Superheated Water Gwen Legate, Chris Alcorn, Jean-Claude Brodovitch, Khashyar Ghandi and Paul Percival Mount Allison University Simon Fraser University Simon Fraser University, TRIUMF Effects of Density Inhomogeneity in Near-Critical Fluids on Muonium Formation Philip Cormier, Khashayar Ghandi, Christopher Alcorn and Gwen Legate Mount Allison University

Monday / Lundi

Monday / Lundi

PREDICITED CORROSION PRODUCT DEPOSITION IN A CANDU®-SCWR FUEL CHANNEL USING AMMONIA FOR ALKALINITY CONTROL Rob Olive and William Cook UNB NEUTRON PRODUCTION IN A SPHERICAL PHANTOM ABOARD THE INTERNATIONAL SPACE STATION Azadeh Tasbaz and Rachid Machrafi University of Ontario Institute of Technology INFLUENCE OF THE PLASTIC SCINTILLATOR THICKNESS ON THE EFFECINECY OF BETA DETECTION IN MIXED FIELDS Khadijeh Pourtangestnai and Rachid Machrafi UOIT An ion trap for -delayed neutron spectrum measurement Nicholas Scielzo, Ryan Yee, Gang Li, Ralph Segel, Peter Bertone, Fritz Buchinger, Jason Clark, John Crawford, Daniel Lascar, Johnathon Schelt, Anthony Levand, Marisa Pedretti, Guy Savard, Dariusz Seweryniak, Mattew Sternberg, Sidney Gulick, Kumar Sharma and Shane Caldwell Lawrence Livermore National Laboratory University of California, Berkeley McGill University Northwestern University University of Chicago University of Manitoba Influence of H2O2 on surface electrochemistry of SIMFUEL in low pH conditions Mayuri Razdan and Dave Shoesmith University of Western Ontario Validation of Uranium-238 Temperature Dependant Cross-Sections in Geant4 for Low Energy Neutrons using the G4NDL High Precision Libraries Liam Russell, Adriaan Buijs and Guy Jonkmans McMaster University AECL

Computational study of Critical Flow in Supercritical Water cooled Reactor systems Madhuri Chatharaju Graduate Student Measurements of Photon Mass Attenuation Coefficients Cody Crewson, Kyung Eun Roh, Bassey Bassey and Chary Rangacharyulu University of Saskatchwan Non-Parametric Study on the Optimization of Thorium Content in a 54-Element Fuel Bundle for use in a CANDU-SCWR David Hummel and David Novog McMaster University Deuterium Isotope Effects on the Ionization Constants of pD Control Agents and Metal Hydrolysis from 95 °C to 275 °C at 20 MPa: Measurements by AC Conductance using Acetic Acid as a Model System Kristy Erickson, Hugues Arcis, Diego Raffa, Gregory Zimmerman and Peter Tremaine University of Guelph Bloomsburg University THE POTENTIAL PRODUCTION OF MOLYBDENUM 99 IN CANDU REACTORS Andrew C. Morreale, David R. Novog and John C. Luxat McMaster University NEUTRONIC ANALYSIS OF INCORPORATED BREEDER BOOSTER IN CANDU-6 REACTORS BENEFITS, CHALLENGES AND DESIGN MODIFICATIONS Bradford Holmes, Mohamed Geweida and Matthew H Kaye

Monday / Lundi

Monday / Lundi

The Analysis of Local Plasticity during Macro-indentation of the Nickel-based Alloy 600 Used in CANDU Steam Generator Tubing Jashanpartap Grewal, Robert Klassen and Vineet Bhakhri Upcoming Student(September 2011) with UNENE M.Eng Associate Professor, Department of Mechanical and Materials Engineering, Faculty of Engineering, The University of Western Ontario, London, Ontario, N6A 5B9, Canada Centre for Advanced Structural Ceramics, Department of Materials, Imperial College London, London, SW7 2AZ, United Kingdom

Monday / Lundi

Monday / Lundi

Tuesday June 7, Mardi 7 juin CNA AGM and Board Meeting 09:00 - 14:00 - Strategy 1 Room

Tuesday June 7, Mardi 7 juin Advanced Reactors and Fuel Cycles 08:00 - 11:30 - Fallsview Studio A Co-chair: Bill Kupferschmidt, Robert Bodner (AECL) 08:00 Remote detection of radioactive materials via Coherent Anti-Stokes Raman Scattering Alexander Chalyk (Passat Ltd) Entropy Generation Minimization for a Packed Bed Reactor in Nuclear Hydrogen Production Kevin Pope, Greg F. Naterer (UOIT) Modeling of a 3-D SCWR unit cell Geneviève Harrisson, Guy Marleau (École Polytechnique) Coffee Break / Pause The Optimization of Thorium Content in a 54Element Fuel Bundle for use in a CANDU-SCWR David Hummel, David R. Novog (McMaster University) Scoping Study of a Thorium Reactor Driven by PWR-Derived Plutonium Yonni Friedlander (McMaster University), Bronwyn Hyland, Geoff Edwards (AECL), John C. Luxat (McMaster University) Enhanced CANDU 6 (EC6): A Proven Mid-Sized reactor with Fuel Cycle Capability Jerry Hopwood, Michael Soulard, Ian J Hastings (AECL)

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Advanced Reactors and Fuel Cycles Paper Abstracts / Sommaires 08:00 -- Fallsview Studio A Remote detection of radioactive materials via Coherent Anti-Stokes Raman Scattering Alexander Chalyk (Passat Ltd) A sensible nonlinear optical method for remote detection of small quantities of radioactive materials such as deuterium, plutonium, uranium-235, uranium enriched in the isotopes of uranium-233 or uranium-235 with concentration >1 ppb at distances greater than 100 m is proposed. The proposed method is based on remote sensing of the chemo-nuclear by-products O3, HNO3, HO2NO2, and NO2 with the molar fractions ~ 5 10-7, 3 10-7, 2 10-7 and 4 10-7 correspondingly, produced by gamma and neutron radiation interacting with the surrounding atmosphere. The possibility of Coherent Anti-Stokes Raman Scattering (CARS) registrationfrom specific trace gases is discussed.

09:00 -- Fallsview Studio A Modeling of a 3-D SCWR unit cell Geneviève Harrisson, Guy Marleau (École Polytechnique) This paper presents the modeling of a 3-D Supercritical Water-Cooled Reactor unit cell. The pre-homogenization of the geometries allows us to reduce the size of the problem without affecting significantly the results of lattice cell calculations. The differences observed between the results of 2-D and 3-D calculations are explained by the isotropic reflective boundary conditions associated with the Z surfaces in the 3-D case. The lattice code DRAGON, which has the ability to solve the 3-D neutron transport equation, has been used in this study.

08:30 -- Fallsview Studio A Entropy Generation Minimization for a Packed Bed Reactor in Nuclear Hydrogen Production Kevin Pope, Greg F. Naterer (UOIT) The thermochemical copper-chlorine (Cu-Cl) cycle is a promising method to produce hydrogen with nuclear energy. In this paper, the fluid flow and heat transfer processes are examined for a packed bed chemical reactor in the Cu-Cl cycle. The heat transfer rate is predicted by a heatmomentum analogy for external flow over a particle, using the friction factor and Reynolds number. The Nusselt number correlation compares well against three prior methods to predict the Nusselt number in a packed bed (for various combinations of the void fraction, Reynolds and Prandtl numbers). The analysis is extended to minimize the entropy generation due to heat transfer and fluid flow irreversibilities in the packed bed reactor.

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10:00 -- Fallsview Studio A The Optimization of Thorium Content in a 54-Element Fuel Bundle for use in a CANDU-SCWR David Hummel, David R. Novog (McMaster University) A new 54-element fuel bundle design has been proposed for use in a Supercritical Water-Cooled Reactor, a conceptual evolution of existing CANDU® reactors. Pursuant to the goals of the Generation IV International Forum, specifically regarding advancement in fuel cycles, the feasibility of optimizing the thorium content within each ring of fuel elements has been studied. 864 unique permutations of thorium and uranium content were modeled with WIMSAECL, and the results were analyzed using non-parametric statistical methods. Key findings include that discharge burnup and coolant void reactivity are inversely related to the total thorium content in the bundle, and that the maximum linear rating and form factor are inversely related to the thorium content in the outermost ring of fuel elements.

Tuesday / Mardi

10:30 -- Fallsview Studio A Scoping Study of a Thorium Reactor Driven by PWRDerived Plutonium Yonni Friedlander (McMaster University), Bronwyn Hyland, Geoff Edwards (AECL), John C. Luxat (McMaster University) This paper investigates the potential uranium savings from operating thorium-fuelled CANDU© reactors driven by PWR-derived plutonium and recycled 233U. Because 233U production in the thorium fuels is optimized at lower exit burnups, less external fissile driver material is required for the operation of the thorium reactors and natural uranium savings of the overall fuel cycle are increased. Assuming the same exit burnup is achieved by reactors with Pu+Th fuel and reactors with 233U+Pu+Th fuel, it was determined that a 40 MWd/kg exit burnup yielded a 52% savings of natural uranium, compared to a scenario in which all power came from PWRs, while a 20 MWd/kg exit burnup increased the savings to 75%.

CANDU© is a registered trademark of Atomic Energy of Canada Limited (AECL).

room which, along with automated testing and on-line diagnostics, make the plant easier and safer to operate, with minimal operator intervention. Containment and seismic capability are upgraded to meet modern standards. The first deployment of the EC6 is anticipated in Canada; international markets are also being pursued. AECL is performing a comprehensive review of the EC6 design in the wake of the Fukushima accident, will review lessons learned, and incorporate any necessary improvements into new build design.

11:00 -- Fallsview Studio A Enhanced CANDU 6 (EC6): A Proven Mid-Sized reactor with Fuel Cycle Capability Jerry Hopwood, Michael Soulard, Ian J Hastings (AECL) Atomic Energy of Canada (AECL) is finalizing development of the Enhanced CANDU 6Ò* (EC6â*), which incorporates the CANDU 6's well-proven features, and adds enhancements that make the reactor even more safe and easier to operate. The EC6 is the only mid-sized reactor (700 MWe class) with a proven pedigree that meets modern reactor expectations and regulatory standards. It is sized for smaller grids and also has outstanding fuel-cycle capability. Changes are incremental and consistent with the CANDU 6 project approach. The EC6 utilizes modern computers and a distributed control system housed in an advanced control

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Tuesday June 7, Mardi 7 juin Plant Life Extension, Refurbishment and Aging 08:00 - 11:00 - Fallsview Studio B Co-chair: Juris Grava (CANTECH Associates Ltd.) 08:00 Future Plans for Performance Analysis and Maintenance/Inspection Optimization of Shutoff Rods Based on the Case Study of Bruce Power Unit-3 Shutoff Rod 5 Inspection Elnara Nasimi (Bruce Power, UOIT), Hossam Gabbar (UOIT) Detailed Finite Element Analysis of Darlington NGS Feeder Pipes With Locally Thinned Regions Below Pressure Minimum Thickness Irfan Haq, Mike Stojakovic, Ming Li (OPG) Robotic Removal of High-Activity Debris from a Nuclear Primary Heat Transfer System Anthony Hamilton, Steve Burany, Samuel Peralta (Kinectrics Inc.), Lindsay Greenland (OPG) Coffee Break / Pause Empirical Observations on the Aging of Flux Detectors at Darlington Constantin Banica, Roman Slovak (OPG) Ultrasonic Detection of Cracks in Pressure Tubes Alex Karpelson (Kinectrics Inc.)

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Plant Life Extension, Refurbishment and Aging Paper Abstracts / Sommaires 08:00 -- Fallsview Studio B Future Plans for Performance Analysis and Maintenance/Inspection Optimization of Shutoff Rods Based on the Case Study of Bruce Power Unit-3 Shutoff Rod 5 Inspection Elnara Nasimi (Bruce Power, UOIT), Hossam Gabbar (UOIT) Shutdown System 1 (SDS1) is a preferred method for a quick shutdown of nuclear fission process in CANDU® (CANada Deuterium Uranium) reactor units. Failure of a routine SDS1 safety test during Fall 2009 outage resulted in the need to develop and execute a new methodology for Shutoff Rod inspection and re-evaluate the known degradation mechanisms and failure modes. This paper describes the development of this methodology and the obtained results. It also proposes several alternative solutions for the future performance analysis and maintenance/inspection optimization for SDS1 Shutoff Rods based on the Bruce Power Unit-3 Shutoff Rod 5 case study.

regions under NB-3200 (NB-3213 & NB-3221) for internal pressure loading only. Detailed finite element models are used for internal pressure analysis using ANSYS v11.0. All other loadings such as deadweight, thermal and seismic loadings are qualified under NB-3600 using a general purpose piping stress analysis software. The piping stress analysis is based on average thickness equal to tmin along with maximum values of ASME Code stress indices (Table NB-3681(a)-1). The requirement for the use of this methodology is that the average thickness of each crosssection with the locally thinned region shall be at least tmin. The finite element analysis models are thinned to 0.75 tmin (in increments of 0.05 tmin) all-around the circumference in the straight section region allowing for flexible inspection requirements. Two different thicknesses of 1.10 tmin and 1.30 tmin are assigned to the bends. Thickness vs the allowable axial extent curves were developed for different types of feeder pipes in service. Feeders differ in pipe size, straight section length, bend angle and orientation. The stress analysis results show that all Darlington NGS outlet feeder pipes are fit for service with locally thinned regions up to 75% of the pressure based minimum thickness. This paper demonstrates the effectiveness of finite element analysis in extending the useful life of degraded piping components.

08:30 -- Fallsview Studio B Detailed Finite Element Analysis of Darlington NGS Feeder Pipes With Locally Thinned Regions Below Pressure Minimum Thickness Irfan Haq, Mike Stojakovic, Ming Li (OPG) Feeder Pipes in CANDU nuclear stations are experiencing wall thinning due to flow accelerated corrosion (FAC) resulting in locally thinned regions in addition to general thinning. In Darlington NGS these locally thinned regions can be below pressure based minimum thickness (tmin), required as per ASME Code Section III NB-3600 Equation (1). A methodology is presented to qualify the locally thinned

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09:00 -- Fallsview Studio B Robotic Removal of High-Activity Debris from a Nuclear Primary Heat Transfer System Anthony Hamilton, Steve Burany, Samuel Peralta (Kinectrics Inc.), Lindsay Greenland (OPG) A unique remote robotic solution, consisting of four singlepurpose robots utilized in series, was used to successfully address the extraction of a high-activity source in the drain line of a nuclear generating station heat exchanger. The source activity was such that safety could be compromised in a manual extraction. In addition, the source was located in a

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confined space, necessitating design of a compact, radiationhard, remotely-controlled solution. This paper reviews the strategy for extraction, design considerations, testing and execution, with a view to providing operational experience for future.

flaw insonification allows detecting the crack and sometimes even "depicting' its shape. Combining obtained data, one can "reproduce" crack shape and orientation, as well as assess its dimensions. Using special software it is possible to generate an isometric (3D) image of a crack.

10:00 -- Fallsview Studio B Empirical Observations on the Aging of Flux Detectors at Darlington Constantin Banica, Roman Slovak (OPG) In-core neutron flux detectors are used for protective and safety functions in the Darlington CANDU reactors. This paper presents observations to date regarding aging of detectors, including recent measurements of prompt fractions and lead cable behaviour during a reactor power rundown. Linear models have been used to estimate and predict the prompt fraction evolution in time using independent variables such as the integrated neutron flux at the detector location, the length of the detector lead cable and the residual current at near-zero flux.

10:30 -- Fallsview Studio B Ultrasonic Detection of Cracks in Pressure Tubes Alex Karpelson (Kinectrics Inc.) Results of the ultrasonic inspection of pressure tubes sometimes are not satisfactory due to inability to detect shallow and narrow cracks. It is therefore worthwhile to develop some special and at the same time simple ultrasonic methods for tubes examination, which could significantly improve inspection capabilities. Combined technique, employing two transducers working in parallel, allows "seeing" crack simultaneously at different angles. The large normal beam probe due to various angles and directions of

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Tuesday June 7, Mardi 7 juin Material Issues 8:00 - 11:30 - Fallsview Studio C Co-chairs: Wenyue Zheng (CANMET-MTL) Mark Daymond (Queens University) 08:00 Feeder Grayloc Hub Local Allowable Thickness A Comparison of ASME Section III and FFSG Appendix E Level 2 Ming Li, Perrik Le Dreff, Ian Wilcox (OPG) The Analysis of Local Plasticity during Macroindentation of the Nickel-based Alloy 600 Used in CANDU Steam Generator Tubing Robert Klassen (U of Western Ontario), Jashanpratap Grewal (U of Western Ontario), Vineet Bhakhri (Imperial College, London) High Temperature Fracture of Candidate Gen IV Reactor Materials Su Xu (CANMET-MTL) Coffee Break / Pause Advanced nuclear corrosion research facilities at CANMET Materials Technology Laboratory in Hamilton J. L. Krausher, W. Zheng (NRCan) Effect of Coating and Surface Modification on Alloy's SCW Corrosion Resistance Jian Li (CANMET-MTL) Electrochemical Study of H2O2 Decomposition on the Magnetite Bulk Electrode Hamidreza Zebardast, Edouard Asselin, Steven Rogak (U of British Columbia)

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Materials, Degredation and Issues Paper Abstracts / Sommaires 08:00 -- Fallsview Studio C Feeder Grayloc Hub Local Allowable Thickness - A Comparison of ASME Section III and FFSG Appendix E Level 2 Ming Li, Perrik Le Dreff, Ian Wilcox (OPG) Flow assisted corrosion (FAC) causes high rates of wall loss at outlet feeder pipes. The most affected area for Darlington outlet feeders is close to the Grayloc end fittings. Inspection data since 2007 identifies that thinning near the Grayloc weld is randomly distributed throughout outlet feeders at the Darlington Nuclear Generation Station (DNGS). The extent of thinning is predicted to reduce the remaining wall below the pressure based (PB) thickness limit for a large portion of the feeder population in the near future. Stress analyses must be performed to demonstrate feeder fitness for service (FFS) with reduced wall thickness as per ASME Section III or other accepted Codes and Standards. The stress analyses using both ASME III (Reference 1) and Fitness For Service Guideline for Feeders (FFSG) Appendix E Level 2 (Reference 2) methodologies were performed under the Localized Feeder Stress Analysis Project (LFSA). It has demonstrated that almost all DNGS outlet feeders have sufficient structural integrity to be declared FFS until the planned Darlington reactor refurbish dates. This results in significant reduction in feeder replacement associated economical cost and personnel radiation dosage. This paper presents the generic methodologies and a comparison of the results of ASME III and FFSG Appendix E Level 2. It demonstrates both the advantages and limitation of the FFSG method.

08:30 -- Fallsview Studio C The Analysis of Local Plasticity during Macroindentation of the Nickel-based Alloy 600 Used in CANDU Steam Generator Tubing Robert Klassen (U of Western Ontario), Jashanpratap Grewal (Student), Vineet Bhakhri (Post-DocFellow) Nano-indents were performed on the cross-sectional plane of the macro-indent made in Inconel-600 alloy to investigate the plastic flow behavior of material in plastic zone around it. Average hardness values were calculated in three directions i.e. vertical, horizontal and diagonal. Both, calculated average hardness and von-mises equivalent plastic strain (obtained from FEM modeling) decrease with increasing distance. Yield stress and von-mises equivalent plastic strain in three directions coincide with the flow curve of the material implying that this type of testing technique can be used to extract the material plastic flow curve as obtained from a conventional mechanical testing method.

09:00 -- Fallsview Studio C High Temperature Fracture of Candidate Gen IV Reactor Materials Su Xu (CANMET-MTL) The likely candidate alloys for the Gen IV nuclear reactors consist of ferritic and martensitic (F/M) high Cr steels (e.g., Grade 91) for construction of high-temperature pipes and nozzles; and austenitic stainless steels, Ni-base alloys, and even oxide dispersion strengthened (ODS) alloys for various in-core components. In this paper, a brief summary is presented of the effects of temperature, stress, loading mode, environment, irradiation, and microstructure on fracture mechanisms and fractographic features of relevant materials. Practical fracture problems with some of these alloys are also discussed.

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10:00 -- Fallsview Studio C Advanced nuclear corrosion research facilities at CANMET Materials Technology Laboratory in Hamilton J. L. Krausher, W. Zheng (NRCan) Research efforts on materials selection and development in support of the design of supercritical water-cooled reactors (SCWRs) have produced a considerable amount of data on corrosion, creep and other related properties. Summaries of the data on corrosion [1] and stress corrosion cracking [2] have recently been produced. As research on the SCWR advances, gaps and limitations in the published data are being identified. In terms of corrosion properties, these gaps can be seen in several areas, including: 1) the test environment, 2) the physical and chemical severity of the tests conducted as compared with likely reactor service/operating conditions, and 3) the test methods used. While some of these gaps can be filled readily using existing facilities, others require the availability of advanced test facilities for specific tests and assessments. In this paper, highlights of the new materials research facilities jointly established in Hamilton by CANMET Materials Technology Laboratory and McMaster University are presented.

Improvement in this alloy is needed in order for it to be considered as a piping construction material. In this report, the development of a metallic coating on a P91 substrate is discussed. Recent effort on selection of in-core cladding alloys has focused on heat-resistant 3xx series stainless steels. These alloys have higher strength at high-temperature ranges, but corrosion and stress-corrosion cracking resistance are a concern. Metallic coating and surface modification are considered as possible solutions to overcome this challenge. The effects of surface modification on the corrosion rate of austenitic steels were also reported in this paper. Asmachined surface showed much better corrosion resistance than polished surface and advanced surface analyses showed distinct differences in the nature and the morphology of the surface layer metal. Possible mechanisms for improved corrosion performance are discussed.

10:30 -- Fallsview Studio C Effect of Coating and Surface Modification on Alloy's SCW Corrosion Resistance Jian Li (CANMET-MTL) Materials selection is one of the key tasks in Gen-IV reactor development. There is no known material that can meet the expected core outlet conditions of the Canadian SCWR concept (625°C core outlet temperature). High-Cr steels with excellent corrosion resistance are often susceptible to embrittlement due to the precipitation of sigma and other phases in the microstructure. Low-Cr steels such as P91 and oxide dispersion strengthened (ODS) steels exhibit good high-temperature mechanical properties, but the lack of sufficient Cr content makes this group alloy corrode too fast.

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11:00 -- Fallsview Studio C Electrochemical Study of H2O2 Decomposition on the Magnetite Bulk Electrode Hamidreza Zebardast, Edouard Asselin, Steven Rogak (U of British Columbia) The high operating temperature and pressure in the heat transport system of Supercritical Water Reactors (SCWRs) can induce fouling in coolant tubes. Magnetite as a major component of foulants has large impacts on the water chemistry and corrosion of these systems since it is known as a catalyzer for decomposition of hydrogen peroxide. This study aimed to investigate the electrochemical kinetics of hydrogen peroxide decomposition on bulk magnetite electrodes using open circuit potential measurement, potentiodynamic and electrochemical impedance spectroscopy methods. Tafel slope and diffusion coefficient were estimated for different concentrations of hydrogen peroxide at pH=9.5 in the 0.1M NaClO4 solution containing 0.01M Na2B4O7 as a buffer.

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Tuesday June 7, Mardi 7 juin Fuel, Spent Fuel, Decommissioning and the Environment 08:00 - 11:00 - Strategy Room 2 Co-chairs: Vicky Skinner (Bruce Power Ltd.) John G. Roberts (CANTECH Associates Ltd) 08:00 Model Support for an Out-ReactorInstrumented-Defected-Fuel-Experiment to Validate the RMC Fuel Oxidation Model Aaron Quastel, Emily Corcoran, Brent Lewis (RMC), Cathy Thiriet (AECL), Gordon Hadaller (Stern Laboratories Inc) Short, Medium and Long Term Consequences of Inadequate Defect Fuel Management John G. Roberts (CANTECH), Rod Nashiem, Maureen McQueen, Guoping Ma (Bruce Power) An Examination of the Time-Dependent Background Counts of the Delayed Neutron Counting System at the Royal Military College of Canada Madison Sellers, Emily Corcoran, David Kelly (RMC) Coffee Break / Pause An ion trap for -delayed neutron spectrum measurement

Nicholas Scielzo (Lawrence Livermore National Laboratory), Ryan Yee (U C, Berkeley), Gang Li (McGill University), Ralph Segel (Northwestern University), Peter Bertone (Argonne National Laboratory), Fritz Buchinger (McGill University), Jason Clark (Argonne National Laboratory), John Crawford (McGill University), Daniel Lascar (Northwestern University), Johnathon Schelt (U of Chicago), Anthony Levand (Argonne National Laboratory), Marisa Pedretti (Lawrence Livermore National Laboratory), Guy Savard, Dariusz Seweryniak (Argonne National Laboratory), Mattew Sternberg (U of Chicago), Sidney Gulick (McGill University), Kumar Sharma (U of Manitoba), Shane Caldwell (U of Chicago)

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An optimization scheme for selecting alternative fuels in CANDU-6 reactor Emmanuel St-Aubin, Guy Marleau (École Polytechnique)

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Fuel, Spent Fuel, Decommissioning and the Environment Paper Abstracts / Sommaires 08:00 -- Strategy Room 2 Model Support for an Out-Reactor-InstrumentedDefected-Fuel-Experiment to Validate the RMC Fuel Oxidation Model Aaron Quastel, Emily Corcoran, Brent Lewis (RMC), Cathy Thiriet (AECL), Gordon Hadaller (Stern Laboratories Inc) An out-reactor fuel oxidation experiment with controlled parameters is being planned to provide data for validation of the Royal Military College (RMC) mechanistic fuel oxidation model. In support of this work, fuel oxidation 2D r-q and 3D models are presented. The 2D r-q model with radial cracks provides the radial temperature distribution in the test fuel element and also provides heating power information. The 3D model with radial cracks and a pelletpellet gap under a defected sheath indicate that an oxygen stoichiometry deviation of 0.057 could result within one week of heating a defected UO2 fuel element with a 5-mm2 sheath defect.

09:00 -- Strategy Room 2 An Examination of the Time-Dependent Background Counts of the Delayed Neutron Counting System at the Royal Military College of Canada Madison Sellers, Emily Corcoran, David Kelly (RMC) A delayed neutron counting (DNC) system for the analysis of special nuclear materials (SNM) has been constructed and calibrated at the Royal Military College of Canada. The polyethylene vials used to transport SNM samples have been found to contribute a time-dependent count rate, B(t), far above the system background. B(t)has been found to be independent of polyethylene mass and shows a dependence on irradiation position in the SLOWPOKE-2 reactor and irradiation time. A comparison of B(t) and the theoretical delayed neutron production from the fission of small amounts of 235U has indicated that trace amounts of uranium may be present in the DNC system tubing.

08:30 -- Strategy Room 2 Short, Medium and Long Term Consequences of Inadequate Defect Fuel Management John G. Roberts (CANTECH), Rod Nashiem, Maureen McQueen, Guoping Ma (Bruce Power) Defect fuel pencils result in short, medium and long term consequences to the environment within and external to the nuclear power station. The paper will describe these consequences and specify the Defect Fuel Management Practices required to avoid these consequences.

10:00 -- Strategy Room 2 An ion trap for -delayed neutron spectrum measurement Nicholas Scielzo (Lawrence Livermore National Laboratory), Ryan Yee (U C, Berkeley), Gang Li (McGill University), Ralph Segel (Northwestern University), Peter Bertone (Argonne National Laboratory), Fritz Buchinger (McGill University), Jason Clark (Argonne National Laboratory), John Crawford (McGill University), Daniel Lascar (Northwestern University), Johnathon Schelt (U of Chicago), Anthony Levand (Argonne National Laboratory), Marisa Pedretti (Lawrence Livermore National Laboratory), Guy Savard, Dariusz Seweryniak (Argonne National Laboratory), Mattew Sternberg (U of Chicago), Sidney Gulick (McGill University), Kumar Sharma (U of Manitoba), Shane Caldwell (U of Chicago) The trap has an open geometry which allows four sets of radiation detectors covering a substantial potion of solid angle. In combination with Microchannel Plate (MCP)

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detector and plastic scintillator detector, BPT is able to measure the beta delayed neutron spectrum to 1% level. A Beta decay Paul Trap (BPT) has been constructed at Argonne National Laboratory for the precise beta decay measurement. We have demonstrated the capability of producing and transferring a low-energy, bunched, and isotopically pure ions beam. In the trap, ions are cooled to sub-eV energies, and confined in a volume of less than 1 mm3.

Tuesday June 7, Mardi 7 juin Reactor Safety and Licensing 08:00 - 11:30 - Strategy Room 3 Co-chair: Ismail Cheng (AMEC-NSS) Parvaiz Akhtar 08:00 On the Functional Failure and Quantification of Margins Dumitru Serghiuta (CNSC) Implementation and Sustainability of a Full Scope Nuclear Power Generator Pressure Boundary QA Program John Krane (Bruce Power) Safety margins in deterministic safety analysis Alexandre Viktorov (CNSC) Coffee Break / Pause Software Development Processes and Analysis Software:A Mismatch and a Novel Framework Diane Kelly (RMC), John Harauz (Jonic Systems Engineering) Minimum Shift Complement: An Important Safety Barrier Suzanne Dolecki, Helen McRobbie (CNSC) Tools to quantify safety culture Bettina Karen Avella (Shumac Latin America)

08:30 10:30 -- Strategy Room 2 An optimization scheme for selecting alternative fuels in CANDU-6 reactor Emmanuel St-Aubin, Guy Marleau (École Polytechnique) We use DRAGON and DONJON codes and standard CANDU-6 models to develop a fuel management calculations sequence based on both time-average and instantaneous approaches that discriminates fuels along the modelling refinement process. This low computer time cost methodology provided various fuel management important quantities, such as average exit burnup and refueling frequency, and criterion for selecting best alternative fuels. The method is applied to natural uranium reference fuel cycle and to an advanced thorium-DUPIC fuel cycle for which we quantify fertile conversion. Results show that viable and exploitable thorium-DUPIC fuel cycle could be an interesting option in CANDU-6 reactor.

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Reactor Safety and Licensingt Paper Abstracts / Sommaires 08:00 -- Strategy Room 3 On the Functional Failure and Quantification of Margins Dumitru Serghiuta (CNSC) This paper reviews some of the modern approaches in treatment and quantification of uncertainties in the context of quantification of margins and potential benefits offered by the use of "functional failure" concept and application of order-statistics modern techniques in safety assessments, as well as some of main areas for R&D. It presents some observations and suggestions aimed at contributing to the debate related to quantification and qualification of margin for CANDU reactors. The views expressed in this paper are those of the author and do not necessarily reflect those of CNSC, or any part thereof. Recent NPPs operating experience shows that in some cases operational and design modifications may lead the plant far away from the original design. Aging and operating life extension, power uprates, new fuel designs with increased performance, such as increased burnup, and R&D discovery issues, as well as cumulative effects of simultaneous or subsequent design changes in a plant, which can be larger than the accumulation of the individual effects of each change, can challenge original safety margins while fulfilling all the regulatory requirements. The aspects related to margin quantification have received a considerable amount of attention from utilities, designers, methodology practitioners, and regulators, due to the significant impact on operation and the need to better evaluate and understand the overall level of safety of operating plants. At the root of the debate are two questions: (1) what is an appropriate framework of criteria and limits, and methods and methodologies for quantification of margins and (2) what are the main areas for new research directions and efforts to reduce the current uncertainties for better economics and improved safety of the current reactors and requirements of the new reactors designs.

08:30 -- Strategy Room 3 Implementation and Sustainability of a Full Scope Nuclear Power Generator Pressure Boundary QA Program John Krane (Bruce Power) In 2009 a new Power Reactor Operating License (PROL) was granted to Bruce Power, Canada's largest independent nuclear power generator. The PROL required the adoption of a large, multi year revision to one of the cornerstone referenced national standards, Canadian Standards Association (CSA) N285.0 and also introduced a new approach to the licensing process and structure. This paper will describe the basis of the new regulatory structure and required pressure boundary related PROL changes and will provide details of the resultant impacts, successful transition, implementation and sustainability of Bruce Power's PBQA Program.

09:00 -- Strategy Room 3 Safety margins in deterministic safety analysis Alexandre Viktorov (CNSC) The concept of safety margins has acquired certain prominence in the attempts to demonstrate quantitatively the level of the nuclear power plant safety by means of deterministic analysis, especially when considering impacts from plant ageing and discovery issues. A number of international or industry publications exist that discuss various applications and interpretations of safety margins. The objective of this presentation is to bring together and examine in some detail, from the regulatory point of view, the safety margins that relate to deterministic safety analysis. In this paper, definitions of various safety margins are presented and discussed along with the regulatory expectations for them. Interrelationships of analysis input and output parameters with corresponding limits are explored. It is shown that the overall safety margin is composed of several components each having different

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origins and potential uses; in particular, margins associated with analysis output parameters are contrasted with margins linked to the analysis input. While these are separate, it is possible to influence output margins through the analysis input, and analysis method. Preserving safety margins is tantamount to maintaining safety. At the same time, efficiency of operation requires optimization of safety margins taking into account various technical and regulatory considerations. For this, basic definitions and rules for safety margins must be first established.

10:30 -- Strategy Room 3 Minimum Shift Complement: An Important Safety Barrier Suzanne Dolecki, Helen McRobbie (CNSC) Adequate staffing is an essential safety barrier for event mitigation. For this reason, Canadian nuclear power plant (NPP) licences specify the minimum staff complement (MSC), which is the number and qualifications of staff always required on-site. A systematic analysis and its validation form the basis of the MSC. The analysis and validation demonstrate a licensee is able to control, cool and contain the reactor after any credible event. The CNSC published regulatory guidelines for analyzing the basis for essential staff levels, monitoring compliance with these levels, and controlling MSC changes (G-323). Lessons learned from a full-scale MSC analysis are discussed.

10:00 -- Strategy Room 3 Software Development Processes and Analysis Software:A Mismatch and a Novel Framework Diane Kelly (RMC), John Harauz (Jonic Systems Engineering) This paper discusses the salient characteristics of analysis software and the impact of those characteristics on its development. From this discussion, it can be seen that mainstream software development processes, usually characterized as Plan Driven or Agile, are built upon assumptions that are mismatched to the development and maintenance of analysis software. We propose a novel software development framework that would match the process normally observed in the development of analysis software. In the discussion of this framework, we suggest areas of research and directions for future work.

11:00 -- Strategy Room 3 Tools to quantify safety culture Bettina Karen Avella (Shumac Latin America) This paper reviews the notion of safety culture and then describes some of the tools that can be used to assess it. Required characteristics to obtain reliable tools and techniques are provided, along with a short summary of the most common and important tools and techniques used to assess safety culture at the nuclear field is described. At the end of this paper, the reader will better understand the importance of the safety culture of the organization and will have requirements to help him in choosing reliable tools and techniques. Further, there will be recommendations on how best to follow-up after an assessment of safety culture.

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Biography / Biographie

Tuesday June 7, Mardi 7 juin Lunch and Honours & Awards Ceremony 11:45 - 14:00 - Great Room A & B Honours and Awards Ceremony

Mr. Frank W. Doyle Executive Chair Director of Research & Development CANDU Owners' Group (COG)

Frank Doyle is the Executive Chair of the Canadian Nuclear Society (CNS) 2011 Annual Conference and the incoming CNS President. He is the current 1st Vice President and the Program Chair for the CNS. Frank was appointed Director of the Research and Development Program for CANDU Owners Group (COG) in 2003. Frank graduated with a degree in Mechanical engineering from Nova Scotia Technical College (Dalhousie University) and an MBA from the University of Toronto. His career in the CANDU nuclear industry includes development, engineering, licensing and project management with senior management positions at Atomic Energy of Canada, Ontario Power Generation and CANDU Owners' Group, Inc. He has held engineering management roles for Bruce , Pickering and CANDU 6 Nuclear Power Plants, as well as overall engineering responsibility for returning Darlington and Bruce plants to high power operation. He has worked on the development of CANDU reactor concepts and continues to be an avid proponent for the future of nuclear power. In addition to his continuing interest in the advancement of nuclear power, Frank has served as a member of the board of directors for several non profit organizations and is a member of the Research Advisory Committee for UNENE.

Tuesday June 7, Mardi 6 juin Keynote Address 14:00 ­ 14:40 - Great Room C 65 Years of Nuclear Safety in Canada

Michael Binder, President and Chief Executive Officer President, Canadian Nuclear Safety Commission

Dr. Michael Binder was appointed in January 2008 as the President and Chief Executive Officer of the Canadian Nuclear Safety Commission (CNSC). He has an extensive career in the federal public service. During his last tenure at Industry Canada, Michael oversaw Canada's transition to a network economy through the regulation of the telecommunication industries, the allocation of Spectrum, the promotion of electronic commerce and the development of the ICT sector. As CNSC President, Michael Binder leads and manages the Commission to protect the health, safety and security of Canadians and the environment, and to implement Canada's international commitments on the peaceful use of nuclear energy. His avowed mission is to ensure that Canadian nuclear facilities and activities are the safest and most secure in the world. Michael Binder holds a Ph.D. in physics from the University of Alberta.

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Biography / Biographie

Tuesday June 7, Mardi 7 juin Plenary II Communicating the Nuclear Message 14:40 - 15:40 - Great Room C Communicating the Nuclear Message: This Session will present the CNA's five-year Strategic Plan, including a renewed Vision, Goal, Guiding Principles, and Core Objectives for Canada's nuclear industry which, based on extensive research, led to the development of the Communications Strategy and Messages. This is being led by the CNA with support and direction provided by leaders from the CNS, WiN, OCI, COG, and industry members. The 2011 Plan includes a social media presence, advertising campaign and strategic partnerships, and also considers the events at Fukushima. Session Moderator: Denise Carpenter, President and CEO, Canadian Nuclear Association Five-Year Strategic Plan - "Dialogue for Understanding and Growth": Sarah Thorne, Principal, Decision Partners Communications Strategy - "Focusing the Dialogue": Kathleen Olson, Director of Communications, Canadian Nuclear Association

Denise Carpenter President and Chief Executive Officer Canadian Nuclear Association

Denise Carpenter was appointed President and CEO of the Canadian Nuclear Association effective November 23, 2009. Prior to this, Ms. Carpenter was Senior Vice President, Public and Government Affairs, with EPCOR Utilities Inc. While at EPCOR, she was responsible for the organization's positioning, reputation strategy and communications that paved the way for the company's transformation into a North American power and water company. She was also responsible for influencing public policy in areas such as climate change/clean air, investment in power transmission infrastructure, the development of near-zero emission power generation from coal, and various public/private partnerships. Before joining EPCOR in 2003, Ms. Carpenter was Executive Vice President and General Manager of Western Canada operations for Weber Shandwick Worldwide. She has made major contributions to Canadian companies seeking to launch, grow, protect and re-position their brands over more than 20 years. Ms Carpenter has extensive experience in the governance of postsecondary institutions and community organizations, as a member and organization leader. She has been honoured by Global TV as a Woman of Vision; by the YWCA with a Woman of Distinction Award; and has twice been named one of Alberta's 50 most influential people by Alberta Venture magazine.

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Biography / Biographie

Biography / Biographie

Sarah Thorne Principal, Decision Partners Kathleen Olson Director of Communications Canadian Nuclear Association

Sarah is a founding partner of Decision Partners and President of the company's Canadian entity, Thorne Butte: Decision Partners Inc. Along with her partner, Gordon Butte, she regularly counsels senior leaders and management teams in formulating behavioural decision strategies and communications to address complex topics. Her practical focus is the design and implementation of science-based stakeholder engagement processes on complex, multi-stakeholder projects. These include siting of thermal electricity facilities, renewable electricity (clean tech/green tech) facilities, new and upgraded transmission, as well as nuclear license renewal and nuclear expansion installations. Much of her work in the energy sector has focused on stakeholder consultation and engagement challenges in Canada and the United States, including her recent work with EPCOR Utilities Inc. and Capital Power Corporation, the Independent Electricity System Operator, the Mining Association of Canada, and the Canadian Nuclear Association, for whom she has supported development of the 5-Year Strategic Plan and supporting Communications Strategy and Plan. She also directed Decision Partners' seminal work on stakeholder engagement and communication in support of the Ontario Power Authority's determination of an electricity supply mix for Ontario and the Integrated Power System Plan (IPSP). With her clients, Sarah is leading the energy sector in developing a systematic approach to enable positive social judgment of new projects and new technologies while avoiding or minimizing the potential for public opposition or social friction (often referred to as "NIMBY"). She has also advised energy associations and their member companies on developing effective strategic risk communications and outreach on environmental and public health challenges. She is a regular contributor to the scientific and management literature on decision and behaviour-focused strategy and communications ­ especially the use of knowledge tools such as expert models and mental models research ­ and frequently speaks on the application of both technologies for strategy and communications design. Sarah is a member of the Canadian Standards Association's Technical Committee on Risk Assessment and Communication, which developed the state-of-the-science guidance on risk management: Q850: Risk Management Guidelines for Decision Makers. She is also a member of the Institute for Risk Research at the University of Waterloo, the Society for Risk Analysis and the Ontario Centres of Excellence ­ Energy Board.

Kathleen Olson joined the CNA in May, 2010 after spending almost 15 years with the Government of Canada working in Communications and Issues Management. In addition to her role as Senior Analyst at the Privy Council Office, Kathleen served as the Director of Communications to the Minister of Natural Resources in 2006-2007, and also held management positions at Natural Resources Canada, Environment Canada, and Human Resources and Skills Development Canada. She has been very active with CNA's membership to develop and implement the CNA's five-year Communications Strategy, Focusing the Dialogue. The Strategy incorporates social media, strategic partnerships, and other innovative vehicles to engage Canadians in a conversation about nuclear technology. Kathleen is originally from Ottawa, Ontario and earned a degree in Mass Communications at Carleton University, and a diploma in Public Relations at Algonquin College. She currently lives in Gatineau, Quebec.

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Tuesday June 7, Mardi 7 juin Plenary III Isotopes and Research Reactors 16:00 - 17:30 - Great Room C Isotopes and Research Reactors: This post coffee break session will address research reactors and Canada's role as an isotope supplier. Session Moderator: Eleodor Nichita, University of Ontario Institute of Technology (UOIT) 16:05 Global Isotope Production and Markets: Richard V. Coté, Vice-President, Commercial, AECL 16:25 Canada's Isotope Strategy: Shannon Quinn, Program Director for Medical Isotopes, Natural Resources Canada 16:45 Planning a New Multi-Purpose Research Reactor for Canada: Jeremy Whitlock, Cochair, CNS Education & Communication Committee and Manager, Non-Proliferation & Safeguards, AECL 17:05 Q & A Period

Eleodor Nichita Associate Professor Faculty of Energy Systems and Nuclear Science University of Ontario Institute of Technology

Past president of the Canadian Nuclear Society B.S., Engineering Physics, University of Bucharest MS in Health Physics and PhD in Nuclear Engineering from Georgia Tech Worked for 6 years in the Reactor Core Physics Branch at AECL Sheridan Park where he was part of the RFSP development team. In 2004 joined the faculty at the University of Ontario Institute of Technology, where he is currently an Associate Professor in the Faculty of Energy Systems and Nuclear Science.

Tuesday June 7, Mardi 7 juin Cocktail Reception and Conference Banquet 18:30 - 22:00 - "Elements on The Falls" Restaurant, at the edge of the falls Have a pleasant walk to the venue or take the shuttle bus in front of the hotel on Falls Avenue C'est une promenade de 15 minutes à pied, ou prenez la navette à l'entrée de l'hôtel sur Falls Avenue

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Biography / Biographie

Biography / Biographie

Shannon Quinn Program Director for Medical Isotopes Natural Resources Canada Richard V. Coté Vice President, Isotopes Business

Shannon Quinn is currently the Program Director for medical isotopes at Natural Resources Canada. She has responsibility for delivering a research, development and demonstration program on non-reactor-based technologies for the production of the isotope technetium-99m. She also contributes to long-term policy development for medical isotopes. Prior to her work on medical isotopes, Shannon was the Program Director for Canada's Generation IV National Program - a long-term nuclear research program. Before joining the federal government in 2006, Shannon worked in the steel industry for six years and concurrently held the position of Adjunct Assistant Professor in the Department of Chemical Engineering at McMaster University. She received a Ph.D. in Chemical Engineering from Queen's University in 1999, and an MBA from the University of Ottawa in 2008.

Richard V. Coté was appointed Vice-President of AECL's Isotopes business in May of 2008. He works closely with Natural Resources Canada and the CNSC with respect to the production of medical Isotopes. Richard is also AECL's representative on the Association of Imaging Producers & Equipment Suppliers ("AIPES") an organization that is working together globally on a strategy and protocol to keep both Canada and the world supplied with isotopes. Prior to that Richard was the Vice-President of Finance and was responsible for line financial management, the corporate financial planning process, corporate procurement and facilities management and worked closely with the risk management team on contracting and business case matters. Richard also is an active member of the Executive Management Team and supports the development of corporate strategies. Richard joined AECL from GE Hydro, where he held many senior positions including VP Finance and VP Sales. During his career at GE, Richard led Corporate acquisitions, risk management planning processes, sales teams and held a broad array of finance roles in Canada and internationally. Richard Coté enjoyed an eleven-year career with GE Hydro. While at GE Hydro in Canada, Richard was the General Manager, Hydro Generation Services (Montreal); Chief Financial Officer (Montreal), Director, Marketing, (Montreal) and General Manager, Construction and Engineering Services Division (Toronto). While with GE Hydro Oslo Norway, he held the positions of Director Commercial Operations and Director Finance Integration. Richard Coté earned his B.Sc. in a double major in mathematics and chemistry at the University of Montreal. Richard and his wife Gail recently moved to Oakville from Montreal.

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Biography / Biographie

Dr. Jeremy J. Whitlock

Dr. Jeremy Whitlock is a Past President and Fellow of the Canadian Nuclear Society (CNS), a volunteer not-for-profit organization of nuclear professionals and other individuals dedicated to communication on nuclear technology and public-affairs issues. Dr. Whitlock also co-chairs the CNS Education & Communication Committee. He is currently the Manager of Non-Proliferation and Safeguards at Atomic Energy of Canada Limited, with responsibility for ensuring that reactor design at AECL meets international obligations on nuclear weapons non-proliferation. He has worked at AECL since 1994, most of that time as a reactor physicist, associated with both CANDU and research reactor development and support. Dr. Whitlock received a B.Sc. (Physics) from the University of Waterloo in 1988, a M.Eng. (Engineering Physics ­ Nuclear) from McMaster University in 1991, and a PhD (Engineering Physics Nuclear) from McMaster in 1995. Dr. Whitlock is a public speaker and author on nuclear issues, including a regular column in the Bulletin of the Canadian Nuclear Society and The Canadian Nuclear FAQ (www.nuclearfaq.ca), a website of frequently-asked questions (FAQs) on Canadian nuclear technology. He received the CNS' 1999 Education and Communication Award for his work on this website. Dr. Whitlock lives with his wife and three children in Deep River, Ontario, and feels that canoes are the closest humans have come to inventing a perfect machine.

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Wednesday June 8, Mercredi 8 juin Plenary IV Alternative Energy Technologies

Dr. Murray J. Stewart President, Stewart Advantage Consultants Inc. Chair, Temporal Power Limited

Dr. Murray J. Stewart founded Stewart Advantage Consultants Inc. in 1993 specializing in strategic and operational planning; marketing; and business assessment primarily in the energy sector. Stewart Advantage is used as the core company to take on long term management and project assignments. Most recently, Dr. Stewart became Chair of Temporal Power Limited. Temporal Power is a developer of electricity storage systems using a proprietary breakthrough flywheel technology. Temporal Power works with electrical utilities to deliver solutions to a range of challenges including integrating renewable power onto the electrical grid. The company is based in Burlington, Ontario. Dr. Stewart was President of the Energy Council of Canada in 2009 and 2010, and was previously in this position from 2004-2006; following which he was the first Executive Director of World Energy Congress - MONTRÉAL 2010. The Energy Council of Canada, one of 93 Member Committees of the World Energy Council, is a vehicle for strategic thinking, networking and action by senior executives in the private and public sectors that have a broad interest in national, continental and global energy issues. Dr. Stewart has held a variety of positions, throughout a career spanning 41 years, in Canadian government and industry. These include research/policy positions with the Government of Canada; Vice President, Canadian General Electric; Chief Executive, James Howden North America; Chair, President & CEO, Canadian Nuclear Association; and President & CEO, ITER Canada. He is a registered Professional Engineer (Mechanical) with a Ph.D. in Metallurgical Engineering from the University of British Columbia; a Member of the Canadian Nuclear Society, Professional Engineers Ontario, and the Ontario Society of Professional Engineers, and a Life Member of the American Society for Metals and the Canadian Institute of Mining and Metallurgy

8:00 - 09:45 - Great Room C Alternative Energy Technologies: This session will address alternatives to nuclear power generation and technologies that have a synergy with nuclear. Session Moderator: Murray J. Stewart, President, Stewart Advantage Consultants Inc. 8:10 Integrated Energy Systems: William (Bill) Smith, Senior Vice President, Energy Sector, Siemens Canada 8:30 Natural Gas ­ The Future of Shale Gas: Kerry S.B. Guy, P. Eng., Manager, Natural Gas Advocacy, Canadian Association of Petroleum Producers 8:50 Carbon Capture and Storage/Sequestration: Mike Monea, Vice-President, Integrated Carbon Capture and Sequestration Project, SaskPower 9:25 Q & A Period

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Biography / Biographie

Biography / Biographie

Bill Smith Senior Vice President, Energy Sector Siemens Canada Limited

Kerry S.B. Guy, P. Eng., Manager, Natural Gas Advocacy, Canadian Association of Petroleum Producers

Business History: 2010 Canadian Association of Petroleum Producers Manager, Natural Gas Advocacy 2001 Encana Corporation Team Lead, Wheatland Property Team 1986 Numac Energy 1998 Manager, Asset Optimization 1996 Manager, North East British Columbia 1990 Manager, Natural Gas Market Development 1986 Development Engineer 1982 Texaco Canada Resources Academic Background: 1982 Technical University of Nova Scotia B. Eng. (Chemical Engineering) Professional Affiliations: Association of Professional Engineers, Geologists, and Geophysicists of Alberta (APEGGA) Kerry Guy has 28 years of experience in the Canadian upstream energy industry. In that time he has had hands-on experience in all aspects of the oil and gas exploration business, from land sales to product marketing, in all three Western Canadian provinces, and with all varieties of petroleum products including oil sands. Most recently, he managed a large asset team for Encana which was fully deployed on the development one of Encana's Coalbed Methane properties, drilling more than 700 wells in the last 3 years. Stakeholder engagement, sound project management and leading a large multi-disciplined team of professionals were keys to success of this team. In his current role, Kerry is engaged in promoting the benefits of increased natural gas usage on behalf of the Canadian energy industry which has recently unlocked vast unconventional resources through advancements in drilling technologies.

As the Senior Vice President of the Energy Sector in Canada, Mr. Smith is responsible for all Energy Sector operations at Siemens in Canada. Mr. Smith's portfolio encompasses the entire energy value chain, and is served through six operating divisions: Fossil Power ­ gas, steam and nuclear power plants, process controls and advanced combustion technologies Renewables ­ large scale wind power, photovoltaic solar and tidal power Oil and Gas ­ process compression, system solutions and industrial power Energy Service ­ power plant life cycle services, outage management and environmental systems Power Transmission ­ high voltage systems and transformers Power Distribution ­ medium voltage systems, protection and control, smart grid and electric cars Mr. Smith has been instrumental in establishing Siemens as a significant player in the energy sector in Canada, developing a strong installed base and a world-class service strategy in the Renewable Power industry. He has transformed the Siemens Power Transmission and Power Distribution businesses from a small product supplier into a full turnkey operation, with capabilities established across Canada. Mr. Smith's specific expertise in nuclear power plant construction and service has provided Siemens with a leading position in the conventional island segment. Prior to joining Siemens, Mr. Smith worked for twenty-one years at Ontario Hydro and Ontario Power Generation, initially as a Project Engineer at the Bruce and Darlington nuclear plants, rising to the role of Vice President-Supply Chain. Mr. Smith is a Professional Engineer with a Bachelor of Engineering degree (with distinction) from Carleton University and an MBA from York University.

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Biography / Biographie

Michael Monea Vice-president, Integrated Carbon Capture & Sequestration Projects

Michael Monea was appointed vice-president of the Integrated Carbon Capture and Sequestration Projects in October 2008. Prior to his role with SaskPower, Monea was senior vice-president with Canada Capital Energy Corporation. He served as Executive Director of the Petroleum Technology Research Centre at the University of Regina and has held a number of other Executive and technical positions in the oil and gas sector. In 2008 he was appointed into the Society of Petroleum Engineers Distinguished Lecture program as an expert in CO2 storage. Monea holds professional engineer and geoscientist designations and received a Bachelor of Science from the University of Regina. He serves as a board member with the Petroleum Technology Research Centre and is chair of both the South Saskatchewan Geological Resources Advisory Committee and Saskatchewan Conservation Board.

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Biography / Biographie

Wednesday June 8, Mercredi 8 juin Plenary V New Nuclear Technologies 10:15 - 12:00 - Great Room C New Nuclear Technologies: This post coffee break session will be a showcase of new applications and technologies for nuclear. Session Moderator: Tony De Vuono, Senior Vice President and Chief Technology Officer, AECL 10:20 Point Lepreau Refurbishment and Energy Developments in New Brunswick: Blair Kennedy, Vice President, Nuclear, New Brunswick Power 10:40 Small Modular Reactors - Technology and Licensing: Philip O. Moor, Vice President, High Bridge Associates 11:00 NRCan Materials Research in Support of Nuclear Technology: Jennifer Jackman, Director General, CANMET Materials Technology Laboratory, Natural Resources Canada 11:20 Alternative Fuels for CANDU Reactors ­ RU and Thorium Collaborative Initiatives": Zhang Zhenhua, Deputy General Manager, Third Qinshan Nuclear Power Company Ltd. (TQNPC), China 11:45 Q & A Period

Dr. Anthony (Tony) De Vuono Senior Vice-President and Chief Technology Officer

Dr. Anthony (Tony) De Vuono was appointed Senior Vice-President and Chief Technology Officer at Atomic Energy of Canada Limited (AECL) in August 2009. He is responsible for AECL's Technology Group which includes: ACR-1000 Development, Reactor Engineering, the Office of the Chief Engineer and Research & Development, some of which is conducted in collaboration with the Chalk River and Whiteshell Laboratories. Prior to joining AECL, Dr. De Vuono served as Vice-President and Chief Technology Officer at Modine Manufacturing Company in Wisconsin; Staff Scientist at the Lawrence Berkeley National Laboratory (University of California at Berkeley); and Principal Research Scientist at Battelle Memorial Institute in Ohio. In these positions, he was accountable for major global research programs in long-term product development cycles. Dr. De Vuono, who began his career in the U.S. Navy Nuclear Power Program, has also held faculty positions at Ohio State University and the University of Illinois, where he taught nuclear engineering courses at both introductory and advanced levels in areas such as nuclear heat transfer. He has garnered six U.S. patents and has authored numerous publications. Dr. De Vuono obtained a Bachelor of Science in Mechanical Engineering as well as a master's degree and doctorate in nuclear engineering from Ohio State University. He is a Director with the Energy Council of Canada. Dr. De Vuono is married and has four children. His interests include cycling, running, golf and horseback riding.

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Biography / Biographie

Biography / Biographie

Blair Kennedy Vice-President Nuclear New Brunswick Power

Philip O. Moor P.E. High Bridge Associates

Blair Kennedy was appointed Vice President of New Brunswick Power Nuclear in April 2010. NB Power group of companies operates one of North America's most diverse generating systems and interconnected transmission networks. Through its subsidiaries, reliable, safe and economically priced electricity generated at sixteen facilities is delivered via terminals, substations and power lines to more than 370,000 direct and indirect customers within New Brunswick and surrounding markets. NB Power also exports electricity to New England, Quebec, Nova Scotia and Prince Edward Island. During his 35 years at NB Power, Mr. Kennedy held various roles including leadership positions in Generation, Strategic Planning, Distribution and Customer Services with assignments at local, national and international levels. His success drew from his ability to analyze complex business issues, develop comprehensive strategies and produce result in a cooperative environment. Furthermore, Mr. Kennedy incorporates his technical expertise combined with an in-dept financial understanding of the utility sector. Throughout his extensive career with NB Power, Mr. Kennedy has had the opportunity to be a part of many ground breaking projects at NB Power including: · Eel River Construction Project ­ the world's first high voltage direct current converter station. · Dalhousie conversion project ­ converting the Station from coal and oil to Orimulsion. The Station became the first fully operational unit in the world to burn Orimulsion fuel. · New Brunswick's first wind projects ­ the Kent Hills Wind Farm and the Caribou Wind Park. Now, as NB Power Vice President Nuclear, Mr. Kennedy has the opportunity to work on yet another world first, - refurbishing a CANDU-6 at the Point Lepreau Generating Station. Mr. Kennedy holds a Bachelor of Science degree in Mechanical Engineering, recognized as a Beaverbrook Scholar for five years from the University of New Brunswick and is a member of the Canadian Electrical Association and the Association of Professional Engineers of New Brunswick. He also has two publications; "Evaluation of Handling & Combustion Characteristics of Orimulsion in a Commercial Utility Boiler" ASME 1991 and "Conversion of NB Power's Dalhousie Generating Station to Orimulsion Fuel" ASME 1992. He and his wife, Ann currently reside in Fredericton; New Brunswick and have two sons and two grandsons.

Philip O. Moor, P.E., is an internationally recognized expert in nuclear technology, licensing, and business structuring. Mr. Moor has over 30 years experience in the power industry. He has been involved with development, design, engineering, construction, operation, and decommissioning of a variety of nuclear facilities. Mr. Moor has been active in industry activity in preparation for new build nuclear facilities and is very familiar with all nuclear and other advanced reactor technologies. As member of the consulting team at High Bridge Associates (www.hbainc.com), Mr. Moor is active in project management and planning all aspects of large and small new reactor projects worldwide. He has performed independent consulting work for an assortment of nuclear designers, engineers and developers. His experience includes serving as Director ­ Project Management, at GPU Nuclear, where he was responsible for all capital projects the Utility's nuclear generating facilities. As Director of Project Development at "ABB-Equity Ventures" he led new project development teams for power projects in Trinidad, Puerto Rico, Brazil, and the United States including the successful licensing of a large green field electrical generation facility in the Midwestern United States. Mr. Moor was Lead Mechanical Engineer on Owners Engineer team responsible for start up and licensing of Susquehanna Nuclear Station, a $4 billion nuclear plant. He reviewed and accepted turnover of chemical, water treatment, and steam systems. Mr. Moor served as Program Manager responsible for engineering, procurement, and construction of a 40 MUSD 5 MW "swing diesel" facility that could reliably provide backup power for either of two nuclear power units. Mr. Moor has been involved in a variety of SMR (Small Modular Reactor) projects since 2003 when he was the Project Manager for the Galena Alaska SMR project. Mr. Moor Chairs the American Nuclear Society (ANS) President's Special Committee on SMR Licensing Issues. The Committee is comprised of distinguished ANS members including representatives from SMR designers, developers, academia, industry, and government who are working to develop consensus on issues challenging the deployment of SMR technology. Mr. Moor is a frequent speaker at SMR and other nuclear technical conferences. He has been quoted on SMR matters in several publications and has testified before the House Energy and Commerce Committee regarding SMR issues.

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Biography / Biographie

Biography / Biographie

Dr. Jennifer Jackman Director General CANMET Materials Technology Laboratory Minerals and Metals Sector Natural Resources Canada

Dr. Jennifer Jackman is the Director-General of the CANMET Materials Technology Laboratory (CANMET-MTL) within Natural Resources Canada. CANMET-MTL is Canada's principal federal research and development laboratory for structural metals research, including materials for use in automotive applications, clean energy, major infrastructure such as pipelines, defence and eco-materials. CANMET-MTL is well-known for its pilot scale facilities for metallurgy, supporting innovation in steel, aluminum, magnesium and other structural metals for nearly 70 years. In 2005, the federal government announced the relocation of CANMET-MTL from Ottawa to Hamilton in order to support stronger synergies with its clients in both industry and academia. The new CANMET-MTL state-of-the-art laboratory in Hamilton was officially inaugurated on February 23, 2011. Dr. Jackman obtained her PhD in Condensed Matter Physics at the University of Guelph in 1983 and has been with the Public Service since 1986. She is very active in the development of automotive materials research in Canada and involved in national and international collaborations with industry, other governments and universities.

Mr. Zhang Zhenhua Deputy General Manager Third Qinshan Nuclear Powr Co., Ltd, CNNC

198427 60 Mr. Zhang Zhenhua is in charge of TQNPC's management of technology, scientific research & development and key technical improvement projects related to CANDU unit. Mr. Zhang Zhenhua joined Nuclear Power Industry in 1984 and has 27 years experience working in nuclear power plant. As one of the top leader of TQNPC, Mr. Zhang Zhenhua attended the commissioning of Qinshan Phase III Nuclear Power Plant and the later operation management. Besides, he leads the important projects such as the modification of Units output improvement, the cobalt 60 research & development, the spent fuel dry storage and the utilization of recycled uranium etc.

Wednesday / Mercredi

Wednesday / Mercredi

Wednesday June 8, Mercredi 8 juin CNS Luncheon 12:00 - 14:00 - Great Room A & B Wayne Robbins, Honourary Chair to introduce Minister Rob Norris Hon. Rob Norris, Minister Responsible for Innovation; Saskatchewan Power Corporation; and Uranium Development Partnership, Saskatchewan Invitation to Saskatchewan in 2012 Honourary Conference Chair Wayne Robbins: Thank Minister Norris and closing conference remarks.

Wednesday / Mercredi

Wednesday / Mercredi

Biography / Biographie

Biography / Biographie

Robert Watson President and CEO, SaskPower

Honourable Rob Norris

Minister of Advanced Education, Employment and Immigration Minister Responsible for Innovation Minister Responsible for Saskatchewan Power Corporation Minister Responsible for Uranium Development Partnership Saskatchewan Apprenticeship and Trade Certification Commission Innovation Saskatchewan Saskatchewan Opportunities Corporation Saskatchewan Research Council MLA for Saskatoon Greystone

Robert Watson became SaskPower's President and CEO August 16, 2010. Before joining SaskPower, Watson served as President and CEO of SaskTel beginning in November of 2004. Prior to that appointment he held several senior executive positions in the Canadian Telecom industry. He has also held various senior-level roles within telecommunications, as well as the education and community sectors. Previous positions include vice-president of Business Development at GT Group Telecom/360 Networks; executive vice-president, Carrier Services, Engineering, Operations, Customer Service and Chief Quality Officer at Group Telecom; President of Shaw FiberLink Ltd., the telecommunications division of Shaw Communications; President of Shaw Mobilecomm; and President of WIC Connexus. Watson is a graduate in Electrical Technologies from Ryerson University, and has attended the International Executive Development Program at the INSEAD Centre in Fountainbleau, France, as well as the Executive Management Program at Ashridge College in the United Kingdom. He also holds an ICD.D designation from the Institute of Corporate Directors. A recipient of the Saskatchewan Centennial Medal, Watson currently serves as a board member for the Conference Board of Canada and for Prostate Cancer Canada. As well, he is the Chairman of the Board for Information Technology Association of Canada (ITAC). Watson and his wife, Brenda, have two adult children.

Rob Norris was born in Edmonton, Alberta, raised in Red Deer, and completed post-secondary education in both Alberta and Saskatchewan. He moved to Saskatchewan in 1994. As a teen, Mr. Norris played competitive hockey, worked in the lumber industry and completed basic militia training in Saskatchewan. During college, he worked for a community newspaper and as a teaching assistant within the Native Studies program at the University of Lethbridge; and later, in the civil engineering sector. During graduate school, Mr. Norris was a teaching assistant at the University of Saskatchewan (U of S) and taught courses focusing on Canadian government for SIAST and the U of S Extension Division. Mr. Norris also he served as a Legislative Assistant within the Canadian House of Commons with his primary duties being related to foreign policy. He began work at the University of Saskatchewan International in 1999, and between 2004 and 2007 Mr. Norris served as the Co-ordinator of Global Relations at the U of S. He has an M.A. (Alberta, with courses completed in Saskatchewan) and a B.A. with distinction (Lethbridge) in political science, with graduate research relating to Canadian foreign policy. Prior to his election to the Legislature in the 2007 provincial election, Mr. Norris served as the Special Advisor on Innovation to the Saskatchewan Party. He has served on several committees, including as Chair of the Knowledge Industry Committee of the Greater Saskatoon Chamber of Commerce. Mr. Norris is the MLA for the constituency of Saskatoon Greystone. Mr. Norris is married to Dr. Martha Smith-Norris, a history professor at the University of Saskatchewan. Their daughter, Jacqueline, is in grade four.

Wednesday / Mercredi

Wednesday / Mercredi

Biography / Biographie

Wednesday June 8, Mercredi 8 juin Process Systems, Measurement, I & C, and Chemistry 14:00 - 17:30 - Strategy Room 1 Co-chairs: Rod Nashiem (Bruce Power Ltd.) Mike Brett (Ontario Power Generation) 14:00 Tight Fitting Garter Springs - MODAR Mitch King (AECL), Dennis Kazimer (Bruce Power) Reliability Analysis of Digital Instrumentation and Control Systems Arun Veeramany, Mahesh Pandey (U of Waterloo) Electrical, Control and Information Systems in the Enhanced CANDU 6 J. De Grosbois, G. Raiskums, Michael Soulard (AECL) Coffee Break / Pause Application of DCS to New Build CANDU Designs using the G-HIACS vSAFE Platform Victor Gomez, Richard Zurek (AECL), Sunao Masunaga (Hitachi Canada Ltd.), Kazuhiko Ishii (Hitachi, Ltd., Information & Control Systems Company), Paul Eric Marko, Daisuke Tan (Hitachi Canada Ltd.) Deuterium Isotope Effects on Acid Ionization and Transition Metal Hydrolysis at Reactor Conditions by Raman Spectroscopy Michael Yacyshyn, Melerin Madekufamba, Peter Tremaine (U of Guelph) Development of an FPGA-Based Controller for Safety Critical Application A. Xing, J. de Grosbois, V. Sklyar, P. Archer, A. Awwal

Wayne Robbins Chief Nuclear Officer

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Wayne Robbins is the Chief Nuclear Officer at Ontario Power Generation (OPG). OPG is an Ontario-based electricity generation company whose principal business is the generation and sale of electricity in Ontario. Wayne Robbins was appointed to this position June 1, 2009. He reports to Tom Mitchell, President & CEO. Prior to this position Wayne was the Senior Vice President, Darlington Nuclear. He reported to the Chief Nuclear Officer and was responsible for the strategic direction, planning and execution required to achieve nuclear production targets at Darlington. September 2005 he was appointed to the position of Deputy Vice President, Darlington Nuclear reporting to the Senior Vice President of Darlington responsible for support organizations and assisting the Senior Vice President in station oversight. Previously, Wayne was the Director of Operations and Maintenance, Pickering B Nuclear. Wayne's experience in operations, maintenance and success in outages was invaluable in meeting the challenges of the extensive outage program for Pickering B. Before his appointment to Pickering B, Wayne held the same position at Pickering A Nuclear. In 2008, Wayne was named OPG's Power Within Leader of the Year and in 2009, was honoured with the Ontario Energy Association leadership award.

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Wednesday / Mercredi

Wednesday / Mercredi

Process Systems, Measurement, I & C, and Chemistry Paper Abstracts / Sommaires 14:00 -- Strategy Room 1 Tight Fitting Garter Springs - MODAR Mitch King (AECL), Dennis Kazimer (Bruce Power) Annulus spacers are used in CANDUTM reactors to maintain the annular gap between two tubes - an inner pressure tube (PT) and the outer calandria tube (CT). Typically four annulus spacers are used in one fuel channel assembly, each at a specified axial position. Bruce Unit 8 and many other CANDU units were constructed with tight-fitting garter springs (TFGS). The TFGS were not designed to be detected or relocated by the conventional tool, Spacer Location And Repositioning (SLAR) processes. Due to non-optimal `As Left' construction locations for the Bruce Unit 8 TFGS, PT/CT contact has been predicted to occur well prior to its End of Life (EOL). Bruce Power entered a Project with AECL-CRL to design, manufacture & test and implement a new tooling system that would detect and reposition tight fitting annulus spacers.

15:00 -- Strategy Room 1 Electrical, Control and Information Systems in the Enhanced CANDU 6 J. De Grosbois, G. Raiskums, Michael Soulard (AECL) This paper describes the electrical, control, and information system (EC&I) design feature improvements of the Enhanced CANDU 6® (EC6®). These additional features are carefully integrated into the EC6 design platform, and are engineered with consideration of operational feedback, human factors, and leveraging the advantages of digital instrumentation and control (I&C) technology to create a coherent I&C architecture in support of safe and high performance operation. The design drivers for the selection of advanced features are also discussed. The EC6 nuclear power plant is a mid-sized Pressurized Heavy Water Reactor design, based on the highly successful CANDU 6 family of power plants, and upgraded to meet today's Canadian and international safety requirements and to satisfy Generation 3 design expectations.

14:30 -- Strategy Room 1 Reliability Analysis of Digital Instrumentation and Control Systems Arun Veeramany, Mahesh Pandey (U of Waterloo) The NUREG-CR/6942 technical report proposed a Markov state transition model for the main feedwater valve (MFV) controller system as part of a Probabilistic Risk Assessment (PRA) of Digital Feedwater Control System (DFWCS). The proposed model extends the Markov model to allow the use of non-exponential distribution in the time to next output of the controller system responsible for maintaining the water level. This case study demonstrates the general application of semi-Markov process model for digital instrumentation and control systems. System failure probability and mission reliability measures are determined.

Wednesday / Mercredi

16:00 -- Strategy Room 1 Application of DCS to New Build CANDU Designs using the G-HIACS vSAFE Platform Victor Gomez, Richard Zurek (AECL), Sunao Masunaga (Hitachi Canada Ltd.), Kazuhiko Ishii (Hitachi, Ltd., Information & Control Systems Company), Paul Eric Marko, Daisuke Tan (Hitachi Canada Ltd.) This paper summarizes the computer control systems engineering and design activities of Atomic Energy of Canada Limited (AECL®) for the Advanced CANDU Reactor (ACR-1000®,1) utilizing Hitachi's Safety Integrity Level (SIL) 2 vSAFE2 (provnounced "nu-safe") Distributed Control System (DCS) platform. Basic applicability of the Hitachi vSAFE R800FS/HSC800FS product for the ACR1000 DCS has been evaluated by AECL and is also summarized. Finally, this paper provides an overview of the key Hitachi product technologies incorporated into the ACR1000 DCS design.

Wednesday / Mercredi

16:30 -- Strategy Room 1 Deuterium Isotope Effects on Acid Ionization and Transition Metal Hydrolysis at Reactor Conditions by Raman Spectroscop Michael Yacyshyn, Melerin Madekufamba, Peter Tremaine (U of Guelph) This paper reports the preliminary measurements from an experimental study to measure the small differences between light (H2O) and heavy (D2O) water under reactor operating conditions (250-300 oC, 10 MPa), using Raman spectroscopy. The deuterium isotope effect DpK = pKD2O ­ pKH2O, for sodium bisulphate NaDSO4 and phosphoric acid D3PO4, has now been determined at temperatures of 25 oC and 80 oC by measuring the isotropic Raman spectra at different concentrations. The results for the pK and pK at 25 oC agree with the literature, confirming the reliability of the method. High temperature cells have been constructed.

Wednesday June 8, Mercredi 8 juin Reactor and Radiation Physics II 14:00 - 17:30 - Strategy Room 3 Co-chairs: Steve Goodchild (OPG) Darren Radford (AECL) 14:00 Physics Aspects of Reload and Approach-toCritical of the NRU Reactor After Vessel Repair Timothy Leung, Mike Atfield, Xiaolin Wang, Sinh Nguyen, Peter Pfeiffer, Jason Budgell (AECL) Three-Dimensional Discrete Heterogeneous Finite Element Method and Code for Static MultiGroup Neutron Diffusion Elif-Can Aydogdu, Eleodor Nichita (UOIT) A Preliminary Study on BP/CP Uncertainty Analysis of Wolsong CANDU 6 Reactors based upon RFSP-IST Fine Mesh Core Model Hyung-Jin Kim, Dai-Hai Chung, Jong-Hyun Kim (Atomic Creative Technology Co., Ltd.), Sung-Min Kim (KHNP) Coffee Break / Pause Simulations and Imaging Algorithm Development for a Cosmic Ray Muon Tomography System for the Detection of Special Nuclear Material in Transport Containers Cybele Jewett (AECL) End-Flux Peaking Experiment in the ZED-2 Reactor using CANFLEX-RU Julian Atfield, Michael Zeller (AECL) Whole-Core Transport Solutions to A Stylized CANDU-6 Core Problem Dingkang Zhang, Farzad Rahnema (Georgia Institute of Technology), Dumitru Serghiuta (CNSC)

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17:00 -- Strategy Room 1 Development of an FPGA-Based Controller for Safety Critical Application A. Xing, J. de Grosbois, V. Sklyar, P. Archer, A. Awwal In implementing safety functions, Field Programmable Gate Arrays (FPGA) technology offers a distinct combination of benefits and advantages over microprocessor-based systems. FPGAs can be designed such that the final product is purely hardware, without any overhead runtime software, bringing the design closer to a conventional hardware-based solution. On the other hand, FPGAs can implement more complex safety logic that would generally require microprocessorbased safety systems. There are now qualified FPGA-based platforms available on the market with a credible use history in safety applications in nuclear power plants. Atomic Energy of Canada (AECL®), in collaboration with RPC Radiy, has initiated a development program to define a vigorous FPGA engineering process suitable for implementing safety critical functions at the application development level. This paper provides an update on the FPGA development program along with the proposed design model using function block diagrams for the development of safety controllers in CANDU® applications.

Wednesday / Mercredi

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Reactor and Radiation Physics II Paper Abstracts / Sommaires 14:00 -- Strategy Room 3 Physics Aspects of Reload and Approach-to-Critical of the NRU Reactor After Vessel Repair Timothy Leung, Mike Atfield, Xiaolin Wang, Sinh Nguyen, Peter Pfeiffer, Jason Budgell (AECL) The National Research Universal (NRU) reactor at Chalk River shut down on 2009 May 14 and there was a subsequent outage of 15 months to repair leaks from the vessel. On 2010 August 17, NRU returned to full power operation and resumed isotope production. This paper describes the physics aspects of reload, and the approach-tocritical (ATC) tests conducted to restart the reactor safely. Five ATC's, each at a different number of reloaded assemblies, plus a final one before reactor startup, were completed to confirm the calculated physics predictions of the subcritical state and critical point. Activities for preparation of the ATC tests, the responsibilities of the physicists during execution of the ATC's, and plots of neutron signal data during the ATC's are presented. The final measured critical point of CR#14 @190 cm agreed well with the calculated physics prediction of CR#14 @185 cm, or within ~0.5 mk.

sizeable because of the many regions and groups involved. A three dimensional diffusion code was developed which reduces the time taken by such full-core fine-mesh finegroup diffusion calculations by applying the finite-element method to the discrete form of the many-group fine- mesh diffusion equation and thus reducing the number of unknowns. Preliminary tests performed on a highlyheterogeneous three dimensional three-group model found the code to produce pin power results with a maximum error of 3.5% of the maximum pin power value, with an eight-fold reduction in computational time compared to a regular fullcore fine-mesh calculation.

14:30 -- Strategy Room 3 Three-Dimensional Discrete Heterogeneous Finite Element Method and Code for Static MultiGroup Neutron Diffusion Elif-Can Aydogdu, Eleodor Nichita (UOIT) Accurate prediction of the neutron flux and power at the fuel pin level rather than at the fuel- assembly level requires, in principle, lengthy many-group transport-theory calculations using a detailed (fuel-pin level) geometrical representation of the core. Many-group fine-mesh diffusion theory, in conjunction with advanced fuel-pin-cell homogenization techniques, can also be used successfully to predict individual fuel pin powers but the computational effort is still

Wednesday / Mercredi

15:00 -- Strategy Room 3 A Preliminary Study on BP/CP Uncertainty Analysis of Wolsong CANDU 6 Reactors based upon RFSP-IST Fine Mesh Core Model Hyung-Jin Kim, Dai-Hai Chung, Jong-Hyun Kim (Atomic Creative Technology Co., Ltd.), Sung-Min Kim (KHNP) A preliminary study has been conducted to help estimate BP/CP uncertainty of Wolsong CANDU 6 reactors by using the WIMS/DRAGON/RFSP-IST code system. The study is focused on the effects of RFSP-IST core modeling practices, especially, in context of laying out mesh spacings associated with the structural materials in the core. The conceptual approach to figure out the effects of mesh spacing layouts associated with the structural materials is supported by the newly updated code system representing the state-of-the-art CANDU reactor physics theory and methodologies, especially, the DRAGON-IST generated incremental cross sections. The application of RFSP-IST fine mesh core model has been exercised to Wolsong Unit 2 core tracking simulations for about one year period of reactor operations. The results so obtained clearly indicate that the improved validation practices and methodology presented here could be qualified to be incorporated into the entire package of BP/CP uncertainty analysis methodologies in order to enhance the quality and reliability of error estimates related to the various topics, e.g., such as, off-line flux mapping errors.

Wednesday / Mercredi

16:00 -- Strategy Room 3 Simulations and Imaging Algorithm Development for a Cosmic Ray Muon Tomography System for the Detection of Special Nuclear Material in Transport Containers Cybele Jewett (AECL) The Cosmic Ray Inspection and Passive Tomography (CRIPT) collaboration is developing a cosmic ray muon tomography system to identify Special Nuclear Materials (SNM) in cargo containers. In order to gauge the viability of the technique, and to determine the best detector type, GEANT4 was used to simulate the passage of cosmic ray muons through a cargo container. The scattering density estimation (SDE) algorithm was developed and tested with data from these simulations to determine how well it could reconstruct the interior of a container. The simulation results revealed the ability of cosmic ray muon tomography techniques to image spheres of lead-shielded Special Nuclear Materials (SNM), such as uranium or plutonium, in a cargo container, containing a cargo of granite slabs.

(KAERI). These experiments used CANFLEX bundles containing Recovered Uranium (RU) fuel (CANFLEX-RU bundles). [2] CANDU® (CANada Uranium Deuterium) is a registered trademark of AECL.

16:30 -- Strategy Room 3 End-Flux Peaking Experiment in the ZED-2 Reactor using CANFLEX-RU ulian Atfield, Michael Zeller (AECL) This paper describes an end-flux peaking experiment performed in the Zero Energy Deuterium reactor (ZED-2) that provides data appropriate for validating code predictions used for qualification of CANFLEX-RU[1] fuel in CANDU®[2]. The experiment involved the substitution of 7 channels of CANFLEX-RU test assemblies into a natural uranium driver lattice, with a `demountable' CANFLEX-RU bundle positioned in the centre of the central RU channel. Copper foils positioned between adjacent fuel pellets within the demountable bundle were used to derive end-flux peaking factors appropriate for CANFLEX-RU fuel.

[1] CANFLEX® (CANDU FLEXible fuelling) is a registered trademark of AECL and the Korea Atomic Energy Research Institute

Wednesday / Mercredi

17:00 -- Strategy Room 3 Whole-Core Transport Solutions to A Stylized CANDU-6 Core Problem Dingkang Zhang, Farzad Rahnema (Georgia Institute of Technology), Dumitru Serghiuta (CNSC) A stylized CANDU half core with adjuster rods was used to test the accuracy and efficiency of the coarse mesh transport (COMET) code. The benchmark problem consists of 2280 fuel bundles in 190 fuel channels with 8 different burnups. The model includes a total of 21 adjuster rods of 1 type perpendicular to the fuel channels and located on three axial locations. A modified version of the MCNP code was used to generate the response function library in the pre-computation phase, and the COMET was used to compute the global eigenvalue and bundle/pin power distribution. In these calculations, a set of tensor products of orthogonal polynomials were used to expand the neutron angular phase space distributions on the interfaces between coarse meshes. The COMET calculations were compared with the MCNP reference solutions. The comparison showed both the global eigenvalue and bundle/pin power distributions predicated by COMET agrees very well with the MCNP reference solution if the orders of expansion in the two spatial variables and the polar and azimuth angles are 4, 4, 2 and 2. These comparisons indicate that COMET can achieve accuracy comparable to Monte Carlo methods while maintaining computational efficiency significantly (orders of magnitude) faster than that of MCNP.

Wednesday / Mercredi

Wednesday June 8, Mercredi 8 juin Training, Infrastructure, and Communication 14:00 - 17:30 - Fallsview A Co-chairs: Basma Shalaby (UNENE) Cherie Ferrari (Kinectrics) 14:00 Teaching about Energy Use at the University Level as a Way to Discuss Nuclear Power Jason Donev (U of Calgary) Research Study on Typical Feature of the Media Coverage on Nuclear Accidents in the National Newspapers in Japan Tatsuro Tsuchida, Hiroshi Kimura (U of Tokyo) Hitachi DCS Emulator Design to Support NPP Simulator Implementation Yasuhiro Nakashima, Kazuhiko Ishii, Daishun Chiba (Hitachi, Ltd., Information & Control Systems Company) Coffee Break / Pause Inattentional Blindness: Present Knowledge, Recent Research and Implications for the Nuclear Industry Jeff Budau (Bruce Power) Waste Not, Want Not: Used Nuclear Fuel Waste as Fuel for a Thousand Years Peter Ottensmeyer (U of T) C-NET: The Centre for Nuclear Energy Technology John Roberts (U of Manchester)

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Training, Infrastructure, and Communication Paper Abstracts / Sommaires 14:00 -- Fallsview A Teaching about Energy Use at the University Level as a Way to Discuss Nuclear Power Jason Donev (U of Calgary) Alberta is considering getting a nuclear power plant. University science departments can play a significant role in educating the public about various aspects of nuclear power, and electricity usage in general. This paper discusses a novel class on energy production, use and distribution. This large lecture course has 100 students who have little to no technical training in energy. By teaching about energy issues, students become more interested nuclear power as part of the energy production portfolio.

15:00 -- Fallsview A Hitachi DCS Emulator Design to Support NPP Simulator Implementation Yasuhiro Nakashima, Kazuhiko Ishii, Daishun Chiba (Hitachi, Ltd., Information & Control Systems Company) Nuclear Power Plant (NPP) simulators are the main means for operator training and as such are a crucial part of the NPP operation life-cycle.Efficient development and testing of NPP software and design concepts require a robust platform mirroring the design and configuration of the operating plant.DCS Emulator and full-scope simulator (FSS) technologies support both these objectives for the entire NPP life-cycle allowing users and operators to implement, test and use actual control and information software applications and designs.This paper describes Hitachi's latest simulator development and challenges in implementing a DCS emulator to provide a code emulation platform for developing NPP software.

14:30 -- Fallsview A Research Study on Typical Feature of the Media Coverage on Nuclear Accidents in the National Newspapers in Japan Tatsuro Tsuchida, Hiroshi Kimura (U of Tokyo) This study focuses on survey of the characteristics of the media coverage on three well-known nuclear accidents. From a quantitative standpoint of the media reporting, it was revealed that the amount of the articles in the surveyed national newspapers tend to increase soon after accidents happen. Plus, as a qualitative research the author interviewed three leader writers, who suggested that the Japanese nuclear industry should prepare to distribute information more timely and sufficiently. They also answered the PR staff needs to contact journalists regularly in order to recognize their awareness and earn their trust.

16:00 -- Fallsview A Inattentional Blindness: Present Knowledge, Recent Research and Implications for the Nuclear Industry Jeff Budau (Bruce Power) Inattentional blindness can occur when our attention has been assigned to a primary task and not enough attentional resources are left to detect what can be a very important unexpected event. This unexpected event is often something that would be detected under normal conditions. Recent research has shown that perceptual load, and qualities of the unexpected stimulus can impact the occurrence of inattentional blindness. As the nuclear industry has situations of high perceptual load, consideration should be given to the implications of this research.

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Wednesday / Mercredi

16:30 -- Fallsview A Waste Not, Want Not: Used Nuclear Fuel Waste as Fuel for a Thousand Years Peter Ottensmeyer (U of T) sed nuclear fuel waste is a huge source of non-carbon energy, rather than a liability. Less than 0.75% of the energy content in mined uranium is extracted in thermal reactors before the fuel is considered "waste". All of that energy in used fuel and in depleted uranium can be extracted by fast neutrons. The result is a 100,000-fold reduction in long-term radioactive burden of the "waste", and a $ 36 trillion gain in electrical energy from currently stored used CANDU fuel. Worldwide, fast-neutron reactors could replace all carbon sources of electricity and still provide over 1000 years of electrical energy at current global levels from nuclear fuel waste alone.

Wednesday June 8, Mercredi 8 juin Special Session: Strategies to Manage Financial and Safety Risk for CANDU 6 Stations for an Extended 14:00 - 17:30 - Strategy Room 2 Co-chairs: Keith Stratton, Mark McIntyre (Atlantic Nuclear) 14:00 Panel Discussion: Strategies to Manage Financial and Safety Risk for CANDU 6 Stations for an Extended Life Wade Parker (NB Power), Patrice Despiens (Hydro-Quebec), Zhang Zhenhua (TQNPC), Randy Lockwood (ANSL) Plant Life Management at Cernavoda Valerian Sorin Ghelbereu (Cernavoda NPP) Coffee Break / Pause Operational Plan for a Delayed Refurbishment Decision Patrice Desbiens (Hydro-Quebec) Fuel Cycles in CANDU: Security of Supply and Reduced Used Fuel Management Jerry Hopwood, Sermet Kuran, Ian J Hastings (AECL) Evaluation of the Cleaning of the First Side of Steam Generator for WOLSONG Nuclear Power Plant-2 Sung-Min Kim (KHNP)

15:00 15:30 16:00 17:00 -- Fallsview A C-NET: The Centre for Nuclear Energy Technology John Roberts (U of Manchester) The Centre for Nuclear Energy Technology was established as part of the Dalton Nuclear Institute at The University of Manchester in 2009 to focus the UK research on front-end nuclear technologies. This includes plant-life extension, new build, naval propulsion and next generation reactors. Building on £4M of government funding through the North West Development Agency (NWDA), C-NET will act as a hub for nuclear research in the North West of England collaborating with both universities and industry.

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Special Session: Strategies to Manage Financial and Safety Risk for CANDU 6 Stations for an Extended Life Paper Abstracts / Sommaires 16:30 -- Strategy Room 2 Fuel Cycles in CANDU: Security of Supply and Reduced Used Fuel Management Jerry Hopwood, Sermet Kuran, Ian J Hastings (AECL) AECL has had a continuous fuel cycle program for more than 40 years, and anticipates that the next step in the evolution of CANDU fuel cycles will be the introduction of Recovered Uranium (RU), derived from conventional reprocessing. A low-risk RU option that can be applied in the short term comprises a combination of RU and Depleted Uranium (DU), giving a Natural Uranium Equivalent (NUE) fuel. Additionally, work is being done on a Thorium demonstration irradiation and a Thorium-capable CANDU Reactor (TCR). AECL has developed the Enhanced CANDU 6®* (EC6®*) reactor, upgraded from its CANDU 6 design. High neutron economy, on-power refueling and a simple fuel bundle provide the EC6 with the flexibility to accommodate a range of advanced fuels, in addition to its standard natural uranium.

The magnetite layers cause fouling inside the steam generator tubes, leading to reduced heat transfer, as well as increased hydraulic resistance in the steam generator tubes and inlet feeders. These developments have negative effects on the core flow and inlet header temperature and consequently adversely affect the CCP. Before 5,000 EFPD, WNPP-2,3,4 will undergo analysis of the ROP trip setpoint. WNPP-2 will arrive at 5,000 EFPD in 2012. For maximizing the ROP trip setpoint, we are carrying out numerous studies and actions. As a counter action, the present cleaning operation was performed at the optimal time and excellent results were achieved.

17:00 -- Strategy Room 2 Evaluation of the Cleaning of the First Side of Steam Generator for WOLSONG Nuclear Power Plant-2 Sung-Min Kim (KHNP) Mechanical cleaning of the primary side of the WNPP-2 Steam Generator was carried out with AREVA SIVABLAST in December 2010 during a plant outage. All industrial plants undergo changes with time and nuclear plants are no exception. CANDU undergoes increased hydraulic resistance due to redistribution of iron in the HTS. Dissolution of iron and flow accelerated corrosion occur in the outlet feeders.

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Wednesday June 8, Mercredi 8 juin Special Session ­ Fusion 14:00 - 17:30 - Fallsview B Co-chair: Blair Bromley (AECL) 14:00 ASME Division 4 Fusion Energy Devices William Sowder (Quality Management Services), Richard Barnes (Anric) Multi-Group Fusion Reactivities for Maxwellian and Non-Maxwellian Ion Velocity Distributions Rudrodip Majumdar, Manjeet S. Kalra (I.I.T Kanpur) Estimation of Nusselt Number and the First Wall Heat Extraction Capability in Self-Cooled Liquid Metal Blankets Amit. K. Srivastava, Abdul. B. Ahmad, Manjeet S. Kalra (I.I.T Kanpur) Coffee Break / Pause Developing Acoustic Magnetized Target Fusion An Overview of the Science and Development Program at General Fusion Michael Delage, Dan Blondal, Doug Richardson (General Fusion Inc.) Inertial Fusion Energy - Research at the University of Alberta and a Proposed Alberta/Canada Program Robert Fedosejevs, Allan Offenberger, Sanjay Singh, Ying Tsui (U of Alberta) Physical Design and Performance Prediction of the STOR-U Spherical Tokamak Dazhi Liu, Chijin Xiao, Akira Hirose (U of Saskatchewan)

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Special Session ­ Fusion Paper Abstracts / Sommaires 14:00 -- Fallsview B ASME Division 4 Fusion Energy Devices William Sowder (Quality Management Services), Richard Barnes (Anric) There is an on-going effort within the ASME Section III Codes and Standards organization approved by the ASME Board of Nuclear Codes and Standards to develop rules for the construction of fusion-energy-related components such as vacuum vessel (vacuum or target chamber), cryostat and superconductor structures and their interaction with each other. These rules will be found in Division 4 of Section III entitled " Fusion Energy Devices (BPV III)". Other related support structures, including metallic and non-metallic materials, containment or confinement structures, fusionsystem piping, vessels, valves, pumps, and supports will also be covered. The rules shall contain requirements for materials, design, fabrication, testing, examination, inspection, certification, and stamping. The formation of the new Sub-Group Fusion Energy Devices that will develop these rules is just beginning to develop its membership and future working group support structures.

distributions have been considered. The effect of unequal ion kinetic temperatures on the fusion reactivity has also been considered.

15:00 -- Fallsview B Estimation of Nusselt Number and the First Wall Heat Extraction Capability in Self-Cooled Liquid Metal Blankets Amit. K. Srivastava, Abdul. B. Ahmad, Manjeet S. Kalra (I.I.T Kanpur) Self-cooled liquid metal breeding blankets are in principle the simplest type of blankets that can be used in fusion reactors. Two critical issues in such blankets are strong magnetohydrodynamic (MHD) effects and the heat extraction capability from the first wall using liquid metals. In this work we estimate from first principles the MHD friction factors and Nusselt numbers applicable to convective cooling of the first wall using liquid metals. This is followed by a parametric, thermal-hydraulic study of the first wall cooling capability in self-cooled blankets with emphasis on coolant channel dimensions, dynamic pressure drop and heat removal rate to pumping power ratio.

14:30 -- Fallsview B Multi-Group Fusion Reactivities for Maxwellian and Non-Maxwellian Ion Velocity Distributions Rudrodip Majumdar, Manjeet S. Kalra (I.I.T Kanpur) Ion velocity distributions in magnetically confined thermonuclear fusion plasmas under reacting conditions can deviate considerably from Maxwellian distributions. However, fusion reactivities used for power balances in fusion reactors are generally available for two interacting Maxwellian species at the same temperature. In the present work we report total fusion reactivities as well as fractional contributions to these from different ion energy groups, for a number of representative non-Maxwellian ion velocity distributions. Both isotropic as well as anisotropic

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16:00 -- Fallsview B Developing Acoustic Magnetized Target Fusion An Overview of the Science and Development Program at General Fusion Michael Delage, Dan Blondal, Doug Richardson (General Fusion Inc.) Magnetized Target Fusion (MTF) is an alternative approach to fusion which proposes to meet Lawson's criterion for net gain by the rapid compression of a compact toroid plasma using a conductive metal wall. This paper provides an overview of the science behind MTF and General Fusion's systematic development program to design, test, and demonstrate the ability to produce energy using its acoustic MTF technology.

Wednesday / Mercredi

16:30 -- Fallsview B Inertial Fusion Energy - Research at the University of Alberta and a Proposed Alberta/Canada Program Robert Fedosejevs, Allan Offenberger, Sanjay Singh, Ying Tsui (U of Alberta) Fusion Energy is being pursued internationally using a number of different approaches from magnetic confinement energy to inertial confinement fusion (ICF). Recently there has been significant advancement in inertial confinement fusion using laser drivers with the expectation of the demonstration of large fusion yield within the next year or two opening the path to engineering of fusion reactors based on high energy laser drivers. The Laser Plasma Research group at the University of Alberta has been involved in inertial fusion energy (IFE) research for the past few decades. The current status of IFE and the activities of the University of Alberta Research group in this area is reviewed. Funding of IFE related research in Canada has been very limited and Canada has fallen behind in this area. Given the major developments occurring internationally it is time to increase activities in Canada. A plan for an expanded Alberta/Canadian program in IFE in the near future is discussed.

Wednesday June 8, Mercredi 8 juin Nuclear Technology, Fuel, and Materials 14:00 - 17:30 - Fallsview C Co-chairs: John G. Roberts (CANTECH Associates Ltd) Mohamed Younis 14:00 Technology Spin-offs from a CANDU Development Program Stephen Yu (AECL) ZIRCONIUM OXIDE Coatings on P91 and ZIRCALOY (Zr-2.5%Nb) Substrates for use in SCWRs William Cook (U of New Brunswick), Jamie Miles, Rob Hui (NRC) Research and Production Corporation Radiy activities within Canadian nuclear market Ievgenii Bakhmach, Olexander Siora, Vyacheslav Kharchenko, Volodymyr Sklyar (RPC Radiy), Anton Andrashov (Research and Production Corporation Radiy, Ukraine) Coffee Break / Pause An Advanced Engineering Test Reactor for Canada Daniel Meneley, Glenn Harvel (UOIT) Enhanced CANDU 6: Reactor Core Design and Safety Characteristics Michaela Ovanes, Michael Soulard, Mike Cormier (AECL) Evolution of the Enhanced CANDU-6 Monitoring and Control System Design P. Foster, J. Harber, S. Tikku, A. Xing

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15:30 16:00 17:00 -- Fallsview B Physical Design and Performance Prediction of the STOR-U Spherical Tokamak Dazhi Liu, Chijin Xiao, Akira Hirose (U of Saskatchewan) STOR-U (R0 = 55 cm, A = 1.7, Ip = 2 MA) is a spherical tokamak recently proposed to study high beta plasma physics and engineering. In this paper, physical design and performance prediction of the STOR-U are presented. Various equilibria have been obtained to meet different discharge requirements. Eigenvalue expansion technique was employed to optimize the poloidal field system for current start-up with careful consideration given to eddy current effects in the vacuum chamber. Performance prediction is made using ASTRA code. Simulation results reveal that ion temperature increases significantly in NBI heated discharge. Different NBI configurations are also studied.

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Nuclear Technology, Fuel, and Materials Paper Abstracts / Sommaires 14:00 -- Fallsview C Technology Spin-offs from a CANDU Development Program Stephen Yu (AECL) Both Enhanced CANDU 6 (EC6) and ACR-1000 design retain many essential features of the operating CANDU 6 plant design. As well as further-enhanced safety, the design also focuses on operability and maintainability, drawing on valuable customer input and OPEX. The engineering development of the ACR-1000 design has been accompanied by a research and confirmatory testing program. The ACR technology developed during the ACR-1000 Basic Engineering Program and the supporting development testing has extended the database of knowledge on the CANDU design. This paper provides a summary of technology arising from the ACR program that has been incorporated into new CANDU designs such as the Enhanced CANDU 6 (EC6), or can be applied for servicing operating CANDU reactors.

showed a reduced weight gain at all exposure times when compared to uncoated samples however SEM work reveals that poor coating adhesion resulted in degradation of the coating through oxide loss by spallation or dissolution processes.

15:00 -- Fallsview C Research and Production Corporation Radiy activities within Canadian nuclear market Ievgenii Bakhmach, Olexander Siora, Vyacheslav Kharchenko, Volodymyr Sklyar, Anton Andrashov (RPC Radiy) This paper presents key results of RPC Radiy activities within Canadian nuclear market. RPC Radiy (located in Kirovograd, Ukraine) is a vendor which designs and produces digital safety I&C platform as well as turnkey applications, based on the platform, for NPPs (safety systems). The main feature of the Radiy Platform is the application of Field Programmable Gates Arrays (FPGA) as programmable components for logic control operations. Since 2009 RPC Radiy started to explore the possibility to conduct the expansion to Canadian nuclear market. The activities performed by RPC Radiy related to this direction are resulted in several joint projects with Canadian companies.

14:30 -- Fallsview C ZIRCONIUM OXIDE Coatings on P91 and ZIRCALOY (Zr-2.5%Nb) Substrates for use in SCWRs William Cook (U of New Brunswick), Jamie Miles, Rob Hui (NRC) The CANDU-SCWR presents difficult operating conditions for materials of construction and innovative methods, such as corrosion-resistant coatings, are being developed for reactor materials. In this study, Zircaloy (Zr-2.5%Nb) and P91 were coated with tightly adhering layers of zirconium-based oxides (ZrO2 or Zr-NbO2) through a plasma spray deposition (PSD) process. The coupons were exposed to deoxygenated supercritical water at 500oC and 25 MPa for increasing durations, up to 900 hours. Coated coupons

Wednesday / Mercredi

16:00 -- Fallsview C An Advanced Engineering Test Reactor for Canada Daniel Meneley, Glenn Harvel (UOIT) Recent advances in Gen III+ reactors, programs to develop Gen-IV reactors, and more stringent codes and standards have increased the importance of test facilities for future power plants. However, testing in present day nuclear facilities is difficult due to both current safety requirements and the need to focus on operations. Instead of developing a specialized or multi-purpose research reactor, a new approach is suggested. The authors have developed the conceptual design of an Engineering Test Reactor, with the

Wednesday / Mercredi

purpose of demonstrating objectively the performance of concept designs, prototypes, and endurance testing for components and subsystems of nuclear power plants.

16:30 -- Fallsview C Enhanced CANDU 6: Reactor Core Design and Safety Characteristics Michaela Ovanes, Michael Soulard, Mike Cormier (AECL) This paper outlines the basis for CANDU core safety, based on generic reactor physics characteristics, and presents the specific EC6 enhancements to reactor core and physics design to ensure a robust safety case. The Enhanced CANDU 6® (EC6®) nuclear power plant is a mid-sized Pressurized Heavy Water Reactor design, based on the highly successful CANDU® 6 family of power plants, upgraded to meet today's Canadian and international safety requirements and to satisfy Generation III expectations. Atomic Energy of Canada Limited (AECL®) is completing the development and pre-project review of this design in readiness for new build projects this decade. The EC6 is based on natural uranium fuel, but is able to utilize additional fuel options, including the use of Recovered Uranium (RU or RepU) and Thorium based fuels. The EC6 offers the provenness of the CANDU 6 reference plant design, together with incremental enhancements that provide added benefits in defence-in-depth safety, operating margin, reliable performance and aging management.

Energy of Canada Limited (AECL®) Enhanced CANDU 6® (EC6®) plant design. These enhancements and design approaches ensure that the fundamental premise of independence between safety and process control is not compromised and that the reliability targets for each layer of protection are fulfilled to meet overall plant safety goals. Advances in digital technology and modern human factors engineering principles must be considered by I&C designers without sacrificing the overall principles of defence-in-depth and the independence of safety functions (credited in the safety case). AECL has put a significant amount of effort into applying new technologies to the existing CANDU® 6 (C6) design while taking precautions to retain the original design intent and support the documented safety case.

17:00 -- Fallsview C Evolution of the Enhanced CANDU-6 Monitoring and Control System Design P. Foster, J. Harber, S. Tikku, A. Xing (AECL) This paper describes the enhancements being made to the instrumentation and control (I&C) architecture and design approaches for the display/control systems in the Atomic

Wednesday / Mercredi Wednesday / Mercredi

SPONSORS / APPUI FINANCIER We are pleased to acknowledge and thank the generous financial support provided by: / Nous sommes reconnaissants du généreux appui financier de :

CANMET-MTL

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DISPLAYS / EXPOSITION The CNS thanks the following organisations for reserving display space / La SNC remercie les organisations suivantes d'avoir réservé un espace d'exposition :

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Falls Avenue

FALLSVIEW STUDIO A

STUDIO ROOM PREFUNCTION SPACE

13 foot ceilings

FALLSVIEW STUDIO A FALLSVIEW STUDIO B FALLSVIEW STUDIO C

Exit Corridor

E E E E Business Centre E

To

FALLSVIEW STUDIO B

Women's WR Men's WR

FALLSVIEW STUDIO C

GREAT ROOM PREFUNCTION SPACE

3rd level - Conference Center

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GREAT ROOM C GREAT ROOM B

STAGE GREAT ROOM C DIRECT ENTRANCE TO CASINO NIAGARA GREAT ROOM B

GREAT ROOM A

GREAT ROOM A

18 foot ceilings

Service Hallway

Freight E

UPPER FALLSVIEW STUDIO A

EXECUTIVE BOARDROOM

12 foot ceilings

UPPER FALLSVIEW STUDIO A STRATEGY ROOM 6

EXECUTIVE BOARDROOM

UPPER FALLSVIEW STUDIO B

E STRATEGY ROOM 7 STRATEGY ROOM 5 E E E E

UPPER FALLSVIEW STUDIO B STRATEGY ROOM 6 STRATEGY ROOM 5 STRATEGY ROOM 7 STRATEGY ROOM 3 STRATEGY ROOM 2

UPPER FALLSVIEW / STRATEGY PREFUNCTION SPACE

To

STRATEGY ROOM 4 STRATEGY ROOM PREFUNCTION SPACE

Raised Corridor

5th level - Conference Center

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Men's WR

Women's WR

STRATEGY ROOM 3

STRATEGY ROOM 2

STRATEGY ROOM 1

9 foot ceilings

Service Hallway

Freight E

STRATEGY ROOM 1

Exhibit Layout

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Aecon Nuclear . . . . . . . . . . . . .T9 Anric Enterprises Inc. . . . . .T12 AREVA NP Canada Inc. . . . . . . . . . T6 & T7 Atlantic Nuclear Services Limited . . . . . . . . . . .E4 Atomic Energy of Canada Limited . . . .T10 & T11 Axiom NDT Corporation . . .T2 Babcock & Wilcox Canada . . . . . . . . . . . . . . . . . . .P3 Black & McDonald Limited . . . . . . . . . . . . . . . . . . .P5 Bruce Power . . . . . . . . . . . . . .E3 Cameco Fuel Manufacturing Inc. . . . . . . . .P11

Canadian Nuclear Safety Commission . . . . . . . . .E5 Canadian Nuclear Society . . . . . . . . . . . . . . . . . . .E7 Candesco Corporation . . . . . .T3 Curtiss-Wright Flow Control Nuclear . . . . . . . . . . .P7 EnergySolutions Canada . . . .E1 GE Hitachi Nuclear . . . . . . . .T14 Hatch-Sargent & Lundy Nuclear . . . . . . . . . . . . .T5 Hitachi Canada Ltd. . . . . . . . .T4 Ian Martin Ltd. . . . . . . . . . . . .E2 Industrial Audit Corporation . . . . . . . . . . . . . . .P4

Kanata Electronic Services . . . . . . . . . . . . . . . . . . .E8 Kinectrics Inc. . . . . . . . . . . . . .T1 Mirion Technologies . . . . . . . .P6 NA-YGN . . . . . . . . . . . . . . . . . .E7 Nuclear Logistics Inc. . . . . . . .T8 Organization of CANDU Industries . . . . . . . .T15 SNC-Lavalin Nuclear Inc. . . . . . . . . . . . . . . .P1 UNENE . . . . . . . . . . . . . . . . . . .E7 Westinghouse Electric Company . . . . . . . . .T12 WorleyParsons Canada . . . . .P2 Exhibit Layout

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