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BOOK of EXTENDED SYNOPSES 1400 Vienna, Austria Telephone No.: +43 1 2600 (0) Plus Extension Telefax No.: +43 1 26007 Email: Offi [email protected]

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BOOK of EXTENDED SYNOPSES 1400 Vienna, Austria Telephone No.: +43 1 2600 (0) Plus Extension Telefax No.: +43 1 26007 Email: Offi Cial.Mail@Iaea.Org International Conference on Opportunities and Challenges for Water Cooled Reactors in the 21st Century International Atomic Energy Agency Vienna, Austria, 27–30 October 2009 IAEA-CN-164 P.O. Box 100 Vienna International Centre BOOK OF EXTENDED SYNOPSES 1400 Vienna, Austria Telephone No.: +43 1 2600 (0) plus extension Telefax No.: +43 1 26007 Email: offi [email protected] Painting by Jerrika C. Shi, Aged 10 09-43421 CN-164 Organized by the In cooperation with the EC Joint Research Centre (EC/JRC) International Electrotechnical Commission (IEC) OECD Nuclear Energy Agency (OECD/NEA) World Nuclear Association (WNA) The material in this book has been supplied by the authors and has not been edited. The views expressed remain the responsibility of the named authors and do not necessarily refl ect those of the government of the designating Member State(s). The IAEA cannot be held responsible for any material reproduced in this book. PROGRAMME OVERVIEW Monday Tuesday Wednesday Thursday Friday Time 26 Oct. 2009 27 Oct. 2009 28 Oct. 2009 29 Oct. 2009 30 Oct. 2009 Registration (08:00 – 09:30) Plenary Session Plenary Session Panel Discussion 09:00 - “Design and Construction of Advanced “Safety and Performance Excellence in ”Role of Water Cooled Reactors in the 10:30 st Opening Session Water Cooled Reactors” (Part II) Current NPPs” 21 Century” “Current Nuclear Power Outlook: Opportunities & Challenges" (09:30 – 11:10) 10:30 – Coffee Break Coffee Break (11:10 – 11:30) Plenary Session 11:00 - Topic 1 Topic 2 Topic 3 Topic 2 Topic 4 Topic 5 "Advanced Applications of Water 12:30 Plenary Session Sess. 1-2 Sess. 2-2 Sess. 3-2 Sess. 2-3 Sess. 4-3 Sess. 5-3 “Challenges in Near Term Nuclear Cooled Reactors" Power Deployment” (11:30 – 13:00) 12:30 – Lunch Closing Session 14:00 Lunch (13:00 – 14:00) Plenary Session Panel Discussion 14:00 - Poster Session & Topic 1 . Current Nuclear Power Outlook– “Design and Construction of Advanced “Advanced Monitoring and Diagnostic 15:30 Technical Exhibitions Opportunities to Launch New NPP Water Cooled Reactors” (Part I) Technologies in NPPs” Programme Topic 2 . Nuclear Deployment Challenges and Solutions–Institutional and 15:30 – Coffee Break Cross Cutting Topic 3 . Design and Construction of Advanced Water Cooled Reactors Topic 4 . Safety and Performance 16:00 – Regi- Topic 1 Topic 2 Topic 3 Topic 4 Topic 5 Topic 6 Topic 4 Topic 5 Topic 7 Achievement in Current NPPs 18:00 stration Sess. 1-1 Sess. 2-1 Sess. 3-1 Sess. 4-1 Sess. 5-1 Sess. 6 Sess. 4-2 Sess. 5-2 Sess. 7 Topic 5 . Advanced Technology Application (16:00 – Topic 6 . Safety Assessment in NPPs 19:00) Topic 7 . Instrumentation & Control Welcome Reception Official Dinner 18:30 – (Place : M building) (Place : Melker Stiftskeller Vienna) LIST OF EXTENDED SYNOPSES Number Title of Paper Name of IAEA- Main Author CN-164- Part 1 Synopses for Keynote Presentations 01KS IAEA’s Support of Water Cooled Reactors in the 21st K.S. Kang 3 Century and Beyond S. Bilbao y León O. Glockler 02KS State of Union for Operating Plants: Future Outlook, T. Dujardin Safety Harmonization (Multi-national Design Evaluation Programme) 03KS European Nuclear Safety Research for the Nuclear Giovanni de Santi 5 Renaissance 04KS The Challenge and Countermeasures for Human Mingguang Zheng 7 Resources Development on Nuclear Power in 21st Century 05KS Nuclear Power: an Irreplaceable Option for Sustainable Philippe Pradel 8 Development 06KS Challenges Faced by Developing Countries in Nuclear Hamad Alkaabi 10 Power Deployment 07KS Advanced Nuclear Power Plants in Korea Jong Shin Kim 12 08KS ABWR Technology & Construction Experiences / Masaharu Hanyu 14 Experience of ABWR Operation and Global Deployment Takeo Shimizu 16 09KS Design and Construction of Advanced PHWR Ala Alizadeh 10KS VVER Reactors : Clean and Reliable Source of Energy in Nikolay Trunov 18 the Past and in the Future 11KS Advanced Design of Mitsubishi PWR Plant for Nuclear Etsuro Saji 20 Renaissance 12KS AP1000 Simplicity and Certainty Anders Jackson 13KS Application of Advanced Technology to Improve Plant Hash M. 22 Performance Hashemian 14KS Nulife - its Role in Implementing Strategic Research of Rauno Rintamaa 24 LTO Related to PLiM Issues in Europe 15KS Utility Perspective on Future of Water Cooled Reactors Michael Baron 16KS Hydrogen Production using Water Cooler Reactors Pascal Yvon 26 17KS Innovative Water Cooled Reactor Concepts – Small and Jose Reyes 28 Medium Reactors 18KS Research and Development of Supercritical Water Cooled Yoshiaki Oka 30 Reactors Part 2 Synopses for Oral Presentations TOPIC 1: CURRENT NUCLEAR POWER OUTLOOK: OPPORTUNITIES TO LAUNCH NEW NPP PROGRAMME 1S01 Approaches to Assess Competitiveness of Small and V. Kuznetsov 36 Medium Sized Reactors 1S02 Outlook of Nuclear Energy in Algeria B. Meftah 38 1S03 Implementation of the Visaginas Nuclear Power Plant G. Klevinskas 39 Project in Lithuania 1S04 On the Sustainability of LWR Development in China W. Shen 41 1S05 Regional Approach to the Introduction of Nuclear Power S. Elegba 43 Plants in Africa: Challenges and Opportunities 1S06 Future of the Nuclear Power Generation in Hungary T.J. Katona 44 1S07 Infrastructure Development and Challenges to Launch S. Keinmeesuke 46 Nuclear Power Programme in Thailand 1S08 Evaluation on the Status of Indonesia Nuclear B.Suprawoto 48 Infrastructure Development TOPIC 2: NUCLEAR DEPLOYMENT CHALLENGES AND SOLUTIONS - INSTITUTIONAL AND CROSS CUTTING 2S01 Challenges and Opportunities to Introduce a First Nuclear M.M. Haque 52 Power Plant in Bangladesh 2S02 Nuclear Power Development, Financing and Delivery A. Alizadeh 55 2S03 Nuclear Power for Future Electricity Generation in Ghana: B.J.B. Nyarko 57 Issues and Challenges 2S04 Challenges and Opportunities in Launching New Nuclear H.-G. Kim 58 Power Programs in Developing Countries 2S05 Sustainability of Water Cooled Reactors - Energy Balance A.Strupczewski 61 for Low Grade Uranium Resources 2S06 Challenges and Opportunities to Launch Nuclear Power A. Mikhalevich 63 Programme in Belarus 2S07 Alternatives of Financing for New Nuclear Reactors in L.C. Longoria 65 Mexico 2S08 Expert Performance Transfer: Making Knowledge C.L. Turner 68 Transfer Count 2S09 ACR-1000® PROJECT - Licensing Opportunities and N. Popov 71 Challenges 2S10 The Role of Regulatory Authority in Licensing of the First A.T. Mikulski 73 Nuclear Power Plant 2S11 The Establishment of Regulation for Supporting the A. Mardha 74 Development of the First Nuclear Power Plant in Indonesia 2S12 Human Resources and Training - A Mandatory Gate for O. Salhi 76 Water Cooled Reactors in the 21st Century TOPIC 3: DESIGN AND CONSTRUCTION OF ADVANCED WATER COOLED REACTORS 3S01 Status and Near-Term Works on the EUR Document, P. Berbey 80 Possible Use by Third Parties 3S02 The Enhanced CANDU 6 Reactor - Generation III CANDU S. Azeez 82 Medium Size Global Reactor 3S03 On the Physics Design of Advanced Heavy Water Reactor A. Kumar 84 (AHWR) 3S04 Advanced Construction Technologies and Further J. Kawahata 86 Evolution Towards New Build NPP Projects 3S05 AP1000: The PWR Revisited P. Gaio 88 3S06 Evolution of VVER Technology towards NPP-2006 Project V. Kosogorov 89 3S07 Development of Next-Generation Light Water Reactor in S. Kasai 92 Japan 3S08 Open Issues Associated with Passive Safety Systems L. Burgazzi 94 Reliability Assessment 3S09 Design Characteristics of the Advanced Power Reactor H.G. Kim 96 1400 TOPIC 4: SAFETY AND PERFORMANCE ACHIEVEMENT IN CURRENT NPPS 4S01 Plant Life Management Activities for Long Term Operation M. Marchena 100 of the Argentinean Water Cooled Reactors 4S02 Powering the Future - Life Extension of the Point Lepreau K. P. Stratton 102 Generating Station 4S03 R&D Activities for NPP Life Management in Korea T.R. Kim 104 4S04 Nuclear Power Plant Life Management - Challenges and C. Bruynooghe 106 Proposals for a Unified Model Integrating Safety and Economics 4S05 Long-Term Aging Management Strategies for Nuclear S. G. Toney 109 Power Plants 4S06 Innovative Maintenance Technology for RPV and RIN of N. Suezono 112 Operating Nuclear Plant 4S07 IAEA surveillance data administration within Mat-DB H.H. Over 113 4S08 The Best-Estimate Plus Uncertainty (BEPU) Challenge in F. D'Auria 115 the Licensing of Current Generation of Reactors 4S09 Risk Concept in Nuclear Industry R. Fótos 117 4S10 Application of the Performance Validation Tool for the S.-W. Sohn 119 Evaluation of NSSS Control System Performance 4S11 NULIFE ASSOCIATION: an Opportunity to Face Gen II / V. Prunier 121 Gen III Challenges through Cooperative Research 4S12 Model Reference Control & Protection Theory and A. Cilliers 123 Implementation for Nuclear Power Plants using Real-time Simulations 4S13 Technical Support to An Operating PWR vis- à -vis Safety S. Gul 125 Analysis TOPIC 5: ADVANCED TECHNOLOGY APPLICATION 5S01 CAREM Prototype Construction and Licensing Status D. F. Delmastro 128 5S02 Concept of a High Pressure Boiling Water Reactor, HP- F. Reisch 131 BWR 5S03 Super Critical Water-cooled Nuclear Reactors (SCWRs): I. Pioro 134 Thermodynamic Cycle Options and Thermal Aspects of Pressure-Channel Design 5S04 Conceptual Design of Nuclear CHP Using Absorption G. Heo 136 Cycle 5S05 Water Cooled FBNR Nuclear Reactor F. Sefidvash 138 5S06 Supercritical Water-Cooled Reactor (SCWR) H. Khartabil 140 Development through GIF Collaboration 5S07 Nuclear Co-Generation Desalination Complex with Y. Kuznetsov 142 Simplified Boiling Water Reactor VK-300 5S08 Plutonium Management in Small Nuclear Country P. Dařílek 143 5S09 Roadmap Design for Thorium-Uranium Breeding Recycle S. Si 146 in PWR 5S10 Rod-Type Quench Performance of Nanofluids Towards I. C. Bang 149 Developments of Advanced PWR Nanofluids-Engineered Safety Features 5S11 Applications of Nuclear Energy to Oil Sands and R. B. Duffey 151 Hydrogen Production 5S12 Water Chemistry and Corrosion Prevention at Nuclear V. Yurmanov 152 Plants with Supercritical Water Reactors 5S13 Optimization of CARA Fuel Element with Negative H. A. Lestani 153 Coolant Void Coefficient TOPIC 6: SAFETY ASSESSMENT IN NPPS 6S01 Development of Universal Methodology of Specimen Free M.
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