EUR volume 3 AES 92 subset
|
|
- Millicent Summers
- 6 years ago
- Views:
Transcription
1 European Utility Requirements for LWR nuclear power plants EUR volume 3 AES 92 subset Yury ERMAKOV, RosEnergoAtom Olivier ROUSSELOT, EDF EUR seminar /12/2005
2 key points of the presentation ❽ Presentation of AES 92 design ❽ Main results of AES 92 assessment ❽ Status of subset chapters ❽ Next steps EUR seminar page 2
3 the AES 92 design as licensed by RF GAN for Novovoronezh-2 NPP in 1999 EUR seminar page 3
4 Overall layout of an AES-92 NPP with a VVER-1000 Reactor EUR seminar page 4
5 Main developers of the AES 92 project Federal State Unitary Enterprise Research, Design and Engineering Survey Institute «Atomenergoproekt» Federal State Unitary Enterprise EDO «Gidropress» Federal State Enterprise Russian Scientific Center «Kurchatov Institute» EUR seminar page 5
6 AES 92 Development ❽ USSR Governemt regulation for improving NPP safety ❽ AES 92 design for REA Novovoronezh-2 NPP in Russia Construction license by RF Gan on April 12, 1999 Design approval by Minatom on December 30, 1999 ❽ AES 92 design for NPCIL Kundankulam NPP in India Construction license by Indian AERB on March 22, 2002 First concrete: unit 1: March 2002 unit 1: July 2002 Physical progress achieved (as on October 2005): unit 1 = 61% unit 2 = 52% Scheduled date of criticality: unit 1: 2007 unit 2: 2008 EUR seminar page 6
7 The safety concept: systematic implementation of diversity for all safety functions EUR seminar page 7
8 AES 92 design: main systems EUR seminar page 8
9 AES 92 design: main systems The main active safety systems: Active emergency core cooling + containment spray (pumps + ejectors, 4 trains) active heat removal from steam generator (active steam condenser) active annulus ventilation system EUR seminar page 8
10 AES 92 design: main systems The main passive safety systems: Hydroaccumulators stage 1 (compressed gas driven) Hydroaccumulators stage 2 (gravity driven) Passive heat removal from steam generator (passive steam condenser) Passive annulus filtration system Fast boron injection system EUR seminar page 8
11 AES 92 Containment Passive filtration system Outer wall Reinforced concrete Metallic liner Inner wall Prestressed concrete EUR seminar page 9
12 Corium Catcher Lower plate Cantilever truss Filler Concrete shaft Housing EUR seminar page 10
13 Main results of AES 92 assessment EUR seminar page 11
14 Partners involved in the AES 92 assessment EUR partners: EDF: Mr Olivier ROUSSELOT ENERGOATOM: Mr Vitaly VORONTSOV FORTUM: Mr Bahey MOHSEN IBERDROLA: Mr Carlos PADILLA ROSENERGOATOM: Mr Vadim SEMISHIN Mrs Elena SOLONKO SOGIN: Mr Alceste RILLI VATTENFALL/FKA: Mr Johan ANDERSSON AES 92 Designers: ATOMENERGOPROEKT Mr Mikhail MALTSEV OKB GIDROPRESS: Mr Nikolay FIL KURCHATOV INSTITUTE Several experts EUR seminar page 12
15 first views on volume 3 AES 92 subset From a preliminary survey of AES 92 compliance analyses: ❽ there is a rather good level of compliance with most of the requirements of the chapters of the EUR Volume 2, revision C ❽ in some cases, there is compliance with objectives only Russian Federation specific regulatory context the designer intends to comply in the detailed design phase. ❽ Only several critical issues identified so far EUR seminar page 13
16 first views on volume 3 AES 92 subset Compliance with the EUR objectives: ❽ PSA targets: the results are quite low for the internal events, thus the EUR objectives are reachable, but most internal and external hazards have not been assessed yet ❽ Safety classification: OPB88/97 based on different principles than EUR. The safety classified part may be a bit larger than allowed in EUR. ❽ Primary and Secondary Containment performance: balanced design achievable because of big reserve for optimisation EUR seminar page 14
17 first views on volume 3 AES 92 subset Compliance with the EUR objectives (continued): ❽ Fuel & core performance Average FA Burn-up: 51 MWd/kgHM (55 for EUR) Type of fuel: initially UO 2 core, 50% MOX feasible Length of fuel cycle: initially 12 months, but capability for 24 ❽ Codes & standards: use of Euronorms looks possible ❽ HV Grid requirements: comparable voltage-frequency fields EUR seminar page 15
18 first views on volume 3 AES 92 subset Critical issues that may lead to non-compliances: provisional list; will be further examined for the next few weeks ❽ Plant autonomy beyond 24 hours in case of LOCA + SBO ❽ Spent fuel storage capacity ❽ Refuelling & regular maintenance outage duration ❽ External events: level of Design Basis Earthquake ❽ Reactor vessel design life ❽ I&C and Man-machine interface ❽ Overall construction time EUR seminar page 16
19 Status of the AES 92 subset chapters EUR seminar page 17
20 EUR Volume 3 AES 92 subset Status of the chapters ❽ Chapter 3.1 AES 92 Plant Description November 2005 version available within EUR Organisation ❽ Chapter 3.2 Highlights of the analysis of compliance detailed assessment of compliance being finalised synthesis reports to be approved by EUR SC tomorrow list of the highlighted topics to be finalised before March 2006 ❽ Chapter 3.3 Specific requirements If requested during SC review No text released outside the EUR Organisation so far EUR seminar page 18
21 EUR Volume 3 AES 92 subset Next steps ❽ EUR Harmonisation Review on March 13-15, 2006 Cross checking of AP1000, AES 92 & EPR assessments Revision of the AP1000 and AES92 assessments where needed to ensure consistency ❽ EUR SC#66 on March 23 & 24, 2006 Green light for release of Volume 3 AES 92 subset ❽ Finalisation of the text, preparation of the published version (paper and electronic) ❽ Volume 3 AES 92 subset distribution possibly from June 06 EUR seminar page 19
22 European Utility Requirements for future LWR plants Get fresh news at:
Application of the Defense-in-Depth Concept in the Projects of New-Generation NPPs Equipped with VVER Reactors. JSC ATOMENERGOPROEKT Moscow
Application of the Defense-in-Depth Concept in the Projects of New-Generation NPPs Equipped with VVER Reactors Yu. Shvyryaev V. Morozov A. Kuchumov JSC ATOMENERGOPROEKT Moscow Content General information
More informationOECD/NEA Workshop on "Innovation in Water Reactor Technology
OECD/NEA Workshop on "Innovation in Water Reactor Technology 11-12 February, 2015, Paris Jože Špiler, GEN energija Member EUR Steering Commitee OUTLINE Energy mix policy EUR framework and scope Evolution
More informationDesign, Safety Technology and Operability Features of Advanced VVERs
Technical Cooperation Project INT/4/142 Interregional Workshop on Advanced Nuclear Reactor Technology for Near Term Deployment IAEA Headquarters, Vienna, Austria, 4-8 July 2011 Design, Safety Technology
More informationTechnical potentialities of integration of reactor vessel external cooling in operating WWER-440 plant - Assessment results
Technical potentialities of integration of reactor vessel external cooling in operating WWER-440 plant - Assessment results Speaker Pantyushin S.I. ERMSAR-2013 02-04.10.2013 1. Introduction. Current status
More informationRussian regulatory approach to evaluation of passive systems used for specific BDBA S (SBO, loss of UHS) during safety review of NPP
Federal Environmental, Industrial and Nuclear Supervision Service Scientific and Engineering Centre for Nuclear and Radiation Safety Member of Russian regulatory approach to evaluation of passive systems
More informationUp-to-date issues of VVER Technology Development
Up-to-date issues of VVER Technology Development 10 th International Scientific and Technical Conference Safety, Efficiency and Economics of Nuclear Power industry JSC Concern Rosenergoatom May 25-27,
More informationLight Water Reactor in Russia
ROSATOM STATE CORPORATION ON NUCLEAR ENERGY ROSATOM Light Water Reactor in Russia Presented M.A.Bykov OKB GIDROPRESS 17 th TWG-LWR Meeting, Vienna, 18-20 June 2012 NPP Electricity Generation in Russia
More informationDesign and Construction of Advanced Water Cooled Reactors Evolution of VVER Technology Towards NPP-2006 Project
Design and Construction of Advanced Water Cooled Reactors Evolution of VVER Technology Towards NPP-2006 Project IAEA-CN-164-3S06 V. Kosogorov Energoatom Concern OJSC, Moscow, Russian Federation kosogorov@rosenergoatom.ru
More informationNuclear Power Plant Safety Basics. Construction Principles and Safety Features on the Nuclear Power Plant Level
Nuclear Power Plant Safety Basics Construction Principles and Safety Features on the Nuclear Power Plant Level Safety of Nuclear Power Plants Overview of the Nuclear Safety Features on the Power Plant
More informationNuclear Power Plant Safety Basics. Construction Principles and Safety Features on the Nuclear Power Plant Level
Nuclear Power Plant Safety Basics Construction Principles and Safety Features on the Nuclear Power Plant Level Safety of Nuclear Power Plants Overview of the Nuclear Safety Features on the Power Plant
More informationRosatom Energy Solution: Engineering Perspective
ROSATOM STATE ATOMIC ENERGY CORPORATION ROSATOM Rosatom Energy Solution: Engineering Perspective Rosatom Seminar on Russian Nuclear Energy Technologies & Solutions Alexander Kukshinov Head of External
More informationRussian Federal Nuclear and Radiation Safety Inspectorate (Gosatomnadzor) FEDERAL RULES AND REGULATIONS ON THE USE OF NUCLEAR ENERGY
Translated from Russian Russian Federal Nuclear and Radiation Safety Inspectorate (Gosatomnadzor) FEDERAL RULES AND REGULATIONS ON THE USE OF NUCLEAR ENERGY APPROVED BY Gosatomnadzor Resolution No. 4 of
More informationEPR Safety in the post-fukushima context
EPR Safety in the post-fukushima context October 19 th 2011 Jürgen Wirkner, Peter Volkholz EPR safety approach An accident is a complex series of events: NEED THE MEANS TO REMAIN IN CONTROL OF THE SITUATION,
More informationConcepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant
8 Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant KOZO TABUCHI *1 MASAYUKI TAKEDA *2 KAZUO TANAKA *2 JUNICHI IMAIZUMI *2 TAKASHI KANAGAWA *3 ATMEA1 TM is a 3-loop 1100
More informationStatus and near-term works on the EUR document, possible use by third parties
European Utility Requirements for LWR nuclear power plants International Conference on Opportunities and Challenges for Water Cooled Reactors in the 21st Century Vienna, 27 30 October 2009 IAEA-CN-164-3S01
More informationIn Vessel Retention Strategy VVER 1000/320 VVER 2013 Conference
ÚJV Řež, a. s. In Vessel Retention Strategy VVER 1000/320 VVER 2013 Conference J. Zdarek Presentation content Background of SA issues VVER 1000/320 Containment and RPV Cavity Configuration IVR Strategy
More informationVOLUME 1 MAIN POLICIES AND OBJECTIVES CHAPTER 4 EUR KEY ISSUES
EUROPEAN UTILITY REQUIREMENTS FOR LWR NUCLEAR POWER PLANTS VOLUME 1 MAIN POLICIES AND OBJECTIVES CHAPTER 4 Revision E December, 2016 The EUR promoters assume no liability for any consequences of the use
More informationHarmonized EUR revision E requirements corresponding to currently available technical solutions
Harmonized EUR revision E requirements corresponding to currently available technical solutions Csilla TOTH - EUR Steering Committee MVM Paks II Ltd., Hungary, Technical Director IAEA International Conference
More informationANTICIPATED ANALYSIS OF FLAMANVILLE 3 EPR OPERATING LICENSE - STATUS AND INSIGHTS FROM LEVEL 1 PSA REVIEW
ANTICIPATED ANALYSIS OF FLAMANVILLE 3 EPR OPERATING LICENSE - STATUS AND INSIGHTS FROM LEVEL 1 PSA REVIEW Gabriel Georgescu, Patricia Dupuy and Francois Corenwinder Institute for Radiological Protection
More informationSEVERE ACCIDENT FEATURES OF THE ALTERNATIVE PLANT DESIGNS FOR NEW NUCLEAR POWER PLANTS IN FINLAND
SEVERE ACCIDENT FEATURES OF THE ALTERNATIVE PLANT DESIGNS FOR NEW NUCLEAR POWER PLANTS IN FINLAND Risto Sairanen Radiation and Nuclear Safety Authority (STUK) Nuclear Reactor Regulation P.O.Box 14, FI-00881
More informationProject AES
Project AES-2006 Project AES-2006 2014 Contents I. Introduction...................................................................... 4 II. AES-2006 design concept (described by the example of Leningrad
More informationAssessing and Managing Severe Accidents in Nuclear Power Plant
Assessing and Managing Severe Accidents in Nuclear Power Plant Harri Tuomisto Fortum, Finland IAEA Technical Meeting on Managing the Unexpected - From the Perspective of the Interaction between Individuals,
More informationEvolution of VVER technology towards NPP-2006 project
Evolution of VVER technology towards NPP-2006 project V. Kosogorov Energoatom Concern OJSC Moscow, Russian Federation IAEA 2009.10.28 NPPs of Russia 10 NPPs, 31 units, N =23242 MW Билибинская АЭС Ленинградская
More informationProvision of containment integrity at Russian VVER NPPs under BDBA conditions
Provision of containment integrity at Russian VVER NPPs under BDBA conditions IAEA Technical Meeting Severe Accident Mitigation through Improvements in Filtered Containment Venting for Water Cooled Reactors
More informationPreliminary Lessons Learned from the Fukushima Daiichi Accident for Advanced Nuclear Power Plant Technology Development
Preliminary Lessons Learned from the Fukushima Daiichi Accident for Advanced Nuclear Power Plant Technology Development A. Introduction The IAEA Report on Reactor and Spent Fuel Safety in the Light of
More informationPresent status of Russian nuclear power industry. Future outlook through the analysis of the past
TENTH INTERNATIONAL SCIENTIFIC AND TECHNICAL CONFERENCE SAFETY, EFFICIENCY AND ECONOMICS OF NUCLEAR POWER INDUSTRY Present status of Russian nuclear power industry. Future outlook through the analysis
More informationActivities on Safety Improvement of Czech NPPs in Solution of Severe Accident Issues
Activities on Safety Improvement of Czech NPPs in Solution of Severe Accident Issues Jiří Duspiva ÚJV Řež, a. s. Division of Nuclear Safety and Reliability Dept. of Severe Accidents and Thermomechanics
More informationDESIGN AND SAFETY PRINCIPLES LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION
DESIGN AND SAFETY PRINCIPLES LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION VIENNA OKTOBER 3-6, 2016 1 ANPP * ANPP is located in the western part of Ararat valley 30 km west of Yerevan close to
More informationTechnology Development, Design and Safety Features of the CNP300 and A New Small PWR
Technology Development, Design and Safety Features of the CNP300 and A New Small PWR and A New Small PWR By LIN Qian Shanghai Nuclear Engineering Research and Design Institute (SNERDI) Content SNERDI and
More informationEPR, an Evolutionary Advanced Reactor for a New Nuclear Era. D. REICHENBACH June 2004
EPR, an Evolutionary Advanced Reactor for a New Nuclear Era D. REICHENBACH June 2004 FRAMATOME ANP Second Nato Advanced Research Workshop, Vilnius, June 2004 The European Pressurized Water Reactor EPR
More informationGeneration III of nuclear reactors
Generation III of nuclear reactors Generation III The nuclear reactors technology Summary of the generation III of nuclear reactors technology Actual status of realization Ing. Martin Titka,, Bratislava
More informationState of the Art and Challenges in Level-2 Probabilistic Safety Assessment for New and Channel Type Reactors in India Abstract
State of the Art and Challenges in Level-2 Probabilistic Safety Assessment for New and Channel Type Reactors in India R.S. Rao, Avinash J Gaikwad, S. P. Lakshmanan Nuclear Safety Analysis Division, Atomic
More information3/20/2011. Key technical characteristics
Small reactor technologies of SC ROSATOM 300 According to IAEA classification small-sized reactors are reactors under 300 MWe Electrical output, MWe 100 10 SVBR-10 (12 MWe) SVBR-100 (101 MWe) KLT-40S (38,5
More informationConsiderations on the performance and reliability of passive safety systems for nuclear reactors
January 2016 Considerations on the performance and reliability of passive safety systems for nuclear reactors I. Background Pressurized water reactors currently operating in France are equipped with safety
More informationSafety enhancement of nuclear power plants in Russia: response to challenges of the time
Safety enhancement of nuclear power plants in Russia: response to challenges of the time Alexey Kiryukhin IAEA, Vienna, June 2017 Содержание 1. 1 2. SAFETY ENHANCEMENT OF NPPs IN OPERATION.. 3 NEW DESIGN
More informationTHE MYSTERY OF A REACTOR DISAPPEARANCE: SAFETY ISSUES AND GEN-III NON-COMPLIANCE OF AES-2006 VVER 1000 REACTORS IN FINLAND VT Padmanabhan, R Ramesh, Joseph Makkolil Society of Science Environment and Ethics
More informationINPRO Criterion Robustness of Design Position of the EPR TM reactor Part 3. Franck Lignini Reactor & Services / Safety & Licensing
INPRO Criterion 1.1.1 Robustness of Design Position of the EPR TM reactor Part 3 Franck Lignini Reactor & Services / Safety & Licensing 0 E.P?.?.?.? Robustness against External Hazards 1 External Hazards
More informationSYSTEMATIC AND DESIGN SAFETY IMPROVEMENTS OF NPPS IN CZECH REPUBLIC
SYSTEMATIC AND DESIGN SAFETY IMPROVEMENTS OF NPPS IN CZECH REPUBLIC 3.10.2016 ČEZ, a. s. Meeting at IAEA Vienna Overview of topics ČEZ nuclear fleet (basic features) Systematic measures targeted to improve
More informationRegulatory Review Aspects of Post-Fukushima Safety Enhancements in Indian NPPs
Regulatory Review Aspects of Post-Fukushima Safety Enhancements in Indian NPPs RAHUL PORWAL Atomic Energy Regulatory Board Mumbai, INDIA Outline Introduction AERB Safety Review Methodology Safety Observations
More informationBN-1200 Reactor Power Unit Design Development
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) BN-1200 Reactor Power Unit Design Development B.A. Vasilyev a, S.F. Shepelev a, M.R.
More informationBelgian Stress Test Nuclear Power Plants (BEST)
Belgian Stress Test Nuclear Power Plants (BEST) 2013-08-26 TM IAEA: Belgian Stress Tests Stress Test Specifications Technical scope Initiating events Earthquake Flooding Other extreme natural events (extreme
More informationHPR1000: ADVANCED PWR WITH ACTIVE AND PASSIVE SAFETY FEATURES
HPR1000: ADVANCED PWR WITH ACTIVE AND PASSIVE SAFETY FEATURES D. SONG China Nuclear Power Engineering Co., Ltd. Beijing, China Email: songdy@cnpe.cc J. XING China Nuclear Power Engineering Co., Ltd. Beijing,
More informationRusatom Service experience in LTO of VVER units
Rosatom State Atomic Energy Corporation Rusatom Service experience in LTO of VVER units Nikolay Skirda Plzen, Czech Republic 12.04.2016 Shareholders: transfer of competences Rosenergoatom Electric power
More informationRosatom Global Development, International Cooperation Perspective
ROSATOM STATE ATOMIC ENERGY CORPORATION ROSATOM Rosatom Global Development, International Cooperation Perspective Atomex-Europe 013 Forum Nikolay Drozdov Director, International Business State Corporation
More informationCOMPONENTS DISMANTLING AT NOVOVORONEZH UNITS 1, 2 SHUT DOWN FOR DECOMMISSIONING
COMPONENTS DISMANTLING AT NOVOVORONEZH UNITS 1, 2 SHUT DOWN FOR DECOMMISSIONING Filatov Alexey Engineer, Decommissioning Department Novovoronezh NPP, Russia INTRODUCTION The first phase of Novovoronezh
More informationFormat and Content of the Safety Analysis Report for Nuclear Power Plants - Core Set -
Format and Content of the Safety Analysis Report for Nuclear Power Plants - Core Set - 2013 Learning Objectives After going through this presentation the participants are expected to be familiar with:
More informationSafety Provisions for the KLT-40S Reactor Plant
6th INPRO Dialogue Forum on Global Nuclear Energy Sustainability: Licensing and Safety Issues for Small and Medium-sized Nuclear Power Reactors (SMRs) 29 July - 2 August 2013 IAEA Headquarters, Vienna,
More informationNuclear Construction Summit Developing the recipe for commercial success &
Nuclear Construction Summit Developing the recipe for commercial success & risk assessment Dan Magnarelli Manager, Construction Management Group New Plants Deployment Developing the recipe for commercial
More informationSmall Reactors R&D in China. ZHENG Mingguang Ph D Presented on the meeting of TWG-LWR June 18 th -20 th 2013 IAEA, Vienna
Small Reactors R&D in China ZHENG Mingguang Ph D Presented on the meeting of TWG-LWR June 18 th -20 th 2013 IAEA, Vienna CONTENT 1 Introduction of SMR 2 CAP150 developed by SNERDI/SNPTC 3 CAP FNPP developed
More informationESSENCE AND CHARACTERISTICS OF THE ATMEA TECHNOLOGY: THE ATMEA1 REACTOR
ESSENCE AND CHARACTERISTICS OF THE ATMEA TECHNOLOGY: THE ATMEA1 REACTOR Antoine VERDIER Business Development Manager BULATOM Varna / June 4 th, 2014 An AREVA and MHI Company Introduction ATMEA Company
More informationPRESS CONFERENCE. 3 September Jean-Bernard LÉVY Chairman and CEO. Xavier URSAT Group Senior Executive VP - New Nuclear Projects and Engineering
PRESS CONFERENCE 3 September 2015 Jean-Bernard LÉVY Chairman and CEO Xavier URSAT Group Senior Executive VP - New Nuclear Projects and Engineering EDF, A RESPONSIBLE ELECTRICITY COMPANY, A CHAMPION OF
More informationAKKUYU NGS AŞ. Akkuyu Nuclear Power Plant Progress To-date and the Way Forward. Conference Nuclear Power Asia. Akkuyu NPP Power Generation JSC
Akkuyu Nuclear Power Plant Progress To-date and the Way Forward Conference Nuclear Power Asia Akkuyu NPP Power Generation JSC Why BOO? Pros and Cons What is BOO? Build-own-operate under this scheme, the
More informationPlutonium Management in France. Current Policy and Long Term Strategy for the Used Fuel Recycling by LWR and Fast Reactors
1 Plutonium Management in France Current Policy and Long Term Strategy for the Used Fuel Recycling by LWR and Fast Reactors Christophe XERRI, Nuclear Counsellor 2 3 French Nuclear Fleet 2013 One operator:
More informationCurrent reactor technology, part III: Radek Škoda Czech Technical University Prague WNU SI 2010 Christ Church, Oxford
Current reactor technology, part III: VVER RBMK Radek Škoda Czech Technical University Prague Christ Church, Oxford 1 Overview 1. Gen 1-2-3-4 2. Reactor technology: RBMK 3. Reactor technology: VVER 4.
More informationVVER-440/213 - The reactor core
VVER-440/213 - The reactor core The fuel of the reactor is uranium dioxide (UO2), which is compacted to cylindrical pellets of about 9 height and 7.6 mm diameter. In the centreline of the pellets there
More informationExtension to 60 years lifetime
SFEN Conference Atoms for the future October 22 nd -25 th 2012 Extension to 60 years lifetime J.M.Moroni EDF Nuclear Engineering Division PLIM 2012-14-18 May 2012 - Salt Lake City, USA. Summary Elements
More informationCorium Retention Strategy on VVER under Severe Accident Conditions
NATIONAL RESEARCH CENTRE «KURCHATOV INSTITUTE» Corium Retention Strategy on VVER under Severe Accident Conditions Yu. Zvonarev, I. Melnikov National Research Center «Kurchatov Institute», Russia, Moscow
More informationAdvanced Design of Mitsubishi PWR Plant for Nuclear Renaissance
Advanced Design of Mitsubishi PWR Plant for Nuclear Renaissance October 28, 2009 Etsuro SAJI General Manager, Reactor Core Engineering Department Mitsubishi Heavy Industries, Ltd. GEN-HSW-9102-0 Contents
More informationAdvanced Sodium Fast Reactor Power Unit Concept
International Conference on Fast Reactors and Related Fuel Cycles: Challenges and Opportunities (FR 09) Advanced Sodium Fast Reactor Power Unit Concept V.M. Poplavsky a, A.M. Tsybulya a, Yu.E. Bagdasarov
More informationWestinghouse SMR & Nuclear Fuel Overview
Westinghouse SMR & Nuclear Fuel Overview Carlos Leipner, Westinghouse VP Latin America Presented at LAS-ANS July 2014 Rio de Janeiro, Brasil 2014 Westinghouse Electric Company LLC, All Rights Reserved.
More informationRUSSIAN REGULATORY APPROACH TO EXTENSION OF NUCLEAR POWER PLANT SERVICE LIFE
RUSSIAN REGULATORY APPROACH TO EXTENSION OF NUCLEAR POWER PLANT SERVICE LIFE E.V. Vasileva, N.I. Karpunin Federal State Institution Scientific and Engineering Center for Nuclear and Radiation Safety (SEC
More informationMy name is Yong Soo Kim. I have responsibility for the development of Advanced Nuclear Power
[slide 1] Good afternoon, ladies and gentlemen. My name is Yong Soo Kim. I have responsibility for the development of Advanced Nuclear Power Rectors for Europe, particularly Czech Republic. I wish that
More informationUKEPR Issue 05
Title: PCER Sub-chapter 1.3 Comparison with reactors of similar design Total number of pages: 12 Page No.: I / II Chapter Pilot: P. KRUSE Name/Initials Date 10-10-2012 Approved for EDF by: A. MARECHAL
More informationDepartment of Nuclear Energy. Division of Nuclear Power. Nuclear Power. International Atomic Energy Agency. Akira OMOTO IAEA
Nuclear Power Akira OMOTO Division of Nuclear Power Department of Nuclear Energy IAEA International Atomic Energy Agency blank page.doc 40/1000mm 35/1000mm 40/1000mm 95/1000mm What is nuclear fission?
More informationCOMPREHENSIVE SURVEY OF THE ACTUAL CONDITION AND ASSESSMENT OF THE RESIDUAL OPERATING LIVE OF THE BUILDINGS AND FACILITIES OF KOZLODUY NPP UNITS 5&6
COMPREHENSIVE SURVEY OF THE ACTUAL CONDITION AND ASSESSMENT OF THE RESIDUAL OPERATING LIVE OF THE BUILDINGS AND FACILITIES OF KOZLODUY NPP UNITS 5&6 Надеждност Безопасност Мениджмънт Инженерингови услуги
More informationJoint Stock Company St. Petersburg Research and Design Institute ATOMENERGOPROEKT (JSC SPbAEP) Baltic NPP project in the Kaliningrad region
Joint Stock Company St. Petersburg Research and Design Institute ATOMENERGOPROEKT (JSC SPbAEP) Baltic NPP project in the Kaliningrad region 2011 The Baltic NPP will be constructed in the north-east of
More informationPLUTONIUM UTILIZATION IN REACTOR FUEL
Second Moscow International Nonproliferation Conference PLUTONIUM UTILIZATION IN REACTOR FUEL A. Zrodnikov Director General State Scientific Center of the Russian Federation Institute for Physics and Power
More informationStatus report VVER-1200 (V-491) (VVER-1200 (V-491))
Status report 108 - VVER-1200 (V-491) (VVER-1200 (V-491)) Overview Full name Acronym Reactor type Coolant Moderator Neutron spectrum Thermal capacity Gross Electrical capacity Design status Designers VVER-1200
More informationInnovations and Safety Ensuring in WWERs on the Base of Collaboration on the National and International Levels
IAEA INPRO DF9, Vienna 21 November 2014 Innovations and Safety Ensuring in WWERs on the Base of Collaboration on the National and International Levels Grigory Ponomarenko OKB GIDROPRESS Podolsk, Russian
More informationLife Extension of Russian Nuclear Power Plants
Position Paper, October 2006 Life Extension of Russian Nuclear Power Plants Alexander Nikitin Igor Kudrik www.bellona.org Executive summary Russia is actively implementing a programme to extend the lifetime
More informationCompilation of recommendations and suggestions
Post- Fukushima accident Compilation of recommendations and suggestions Peer review of stress tests performed on European nuclear power plants 26/07/2012 Compilation of Recommendations and Suggestions
More informationSafety of Nuclear Installations Gen 3/3+ October 14, 2011
Safety of Nuclear Installations Gen 3/3+ October 14, 2011 Agenda Introduction to WorleyParsons Safety aspects of Gen III/III+ reactors VVER Design Safety Agenda Introduction to WorleyParsons Safety aspects
More informationAES-2006 PSA LEVEL 1. PRELIMINARY RESULTS AT PSAR STAGE
AES-2006 PSA LEVEL 1. PRELIMINARY RESULTS AT PSAR STAGE A. Kalinkin a*, A. Solodovnikov a, S. Semashko a a JSC "VNIPIET", Saint-Petersburg, Russian Federation Abstract: This report represents PSA level
More informationBasic Engineering Solutions in the VBER-500 Power Unit for Regional Power Systems
Basic Engineering Solutions in the VBER-500 Power Unit for Regional Power Systems A.E. Arefyev, V.V. Petrunin, Yu.P. Fadeev (JSC "Afrikantov OKBM") Yu.A. Ivanov, A.V. Yeremin (JSC "NIAEP") Yu.M. Semchenkov,
More informationReport Regulatory Aspects of Passive Systems - A RHWG report for the attention of WENRA 01 June 2018
Report Regulatory Aspects of Passive Systems - A RHWG report for the attention of WENRA 01 June 2018 Table of Content - 00 Foreword 3 01 Introduction / Goal of the report 5 02 Scope of the Report 6 03
More informationRole and place of the operating organization in implementation of the development strategy of Russian nuclear power industry
THE ELEVENTH INTERNATIONAL SCIENTIFIC AND TECHNICAL CONFERENCE "SAFETY, EFFICIENCY AND ECONOMICS OF NUCLEAR POWER INDUSTRY Role and place of the operating organization in implementation of the development
More informationOpportunities and limits of enhanced co-operation from MDEP experience. Lennart Carlsson Senior Advisor SSM
Opportunities and limits of enhanced co-operation from MDEP experience Lennart Carlsson Senior Advisor SSM MDEP Basics What is MDEP? And why A unique multinational initiative undertaken by national regulatory
More informationTHE ROLE OF PASSIVE SYSTEMS IN ENHANCING SAFETY AND PREVENTING ACCIDENTS IN ADVANCED REACTORS
THE ROLE OF PASSIVE SYSTEMS IN ENHANCING SAFETY AND PREVENTING ACCIDENTS IN ADVANCED REACTORS M. Aziz Nuclear and radiological regulatory authority Cairo, Egypt moustafaaaai@yahoo.com Abstract Most of
More informationTHE FUKUSHIMA ACCIDENT: IMPLICATIONS FOR NUCLEAR SAFETY. Edwin Lyman Union of Concerned Scientists May 26, 2011
THE FUKUSHIMA ACCIDENT: IMPLICATIONS FOR NUCLEAR SAFETY Edwin Lyman Union of Concerned Scientists May 26, 2011 The accident: many unknowns Many of the details of the Fukushima Daiichi accident are still
More informationReactors and Safety. Kudankulam Nuclear Power Plant: How Safe is Safe Enough?
With India s first 1,000 MWe light water reactors at Kudankulam in Tamil Nadu attaining safe criticality on July 13, 2013, the stage is set for electricity generation. While it may take another 30 to 40
More informationNational Status on Life Management of NPPs in Finland Meeting of the IAEA TWG-LMNPP February th 2017 Vienna, Jyrki Kohopää
National Status on Life Management of NPPs in Finland 2017 Meeting of the IAEA TWG-LMNPP February 22-24 th 2017 Vienna, Jyrki Kohopää NUCLEAR POWER IN FINLAND Teollisuuden Voima Oyj, Olkiluoto: OL1/2:
More informationCAREM: AN INNOVATIVE-INTEGRATED PWR
18th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18) Beijing, China, August 7-12, 2005 SMiRT18-S01-2 CAREM: AN INNOVATIVE-INTEGRATED PWR Rubén MAZZI INVAP Nuclear Projects
More informationSTRESS TESTS ACTION PLAN LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION
STRESS TESTS ACTION PLAN LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION VIENNA MARCH 27-29, 2017 1 ANPP * The ANPP is located in the western part of Ararat valley, 30 km west of Yerevan, close
More informationApplicability of PSA Level 2 in the Design of Nuclear Power Plants
Applicability of PSA Level 2 in the Design of Nuclear Power Plants Estelle C. SAUVAGE a, Gerben DIRKSEN b, and Thierry COYE de BRUNELLIS c a AREVA-NP SAS, Paris, France b AREVA-NP Gmbh, Erlangen, Germany
More informationCAREM Prototype Construction and Licensing Status
IAEA-CN-164-5S01 CAREM Prototype Construction and Licensing Status H. Boado Magan a, D. F. Delmastro b, M. Markiewicz b, E. Lopasso b, F. Diez, M. Giménez b, A. Rauschert b, S. Halpert a, M. Chocrón c,
More informationReview of Generation III Reactors
Review of Generation III Reactors Dr. Helmut Hirsch Scientific Consultant for Nuclear Safety Neustadt, Germany 1 Status of Nuclear Power Today (I) Future of nuclear power uncertain. No significant growth
More informationLessons learned from the preparatory process for licensing of the new nuclear units in Hungary
Lessons learned from the preparatory process for licensing of the new nuclear units in Hungary János Krutzler Hungarian Atomic Energy Authority Department of Project Affairs Content Hungary s new NPP project
More informationSevere accidents management in PWRs
Severe accidents management in PWRs J. Rajzrová, J.Jiřičková Abstract According to a new trend in safety upgrades in PWRs, the nuclear power plants have started to adopt strategs to mitigate events beyond
More informationMETHODOLOGY FOR ENSURING THE INTEGRATION OF ALARA INTO THE DESIGN OF
METHODOLOGY FOR ENSURING THE INTEGRATION OF ALARA INTO THE DESIGN OF THE AP1000 TM REACTOR Erik Slobe slobeed@westinghouse.com Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township,
More informationENVIRONMENTAL SAFETY OF NUCLEAR POWER PLANTS OF RUSSIAN DESIGN
International Journal of Mechanical Engineering and Technology (IJMET) Volume 9, Issue 11, November 2018, pp. 172 176, Article ID: IJMET_09_11_019 Available online at http://www.iaeme.com/ijmet/issues.asp?jtype=ijmet&vtype=9&itype=11
More informationDEVELOPMENT AND APPLICATION OF PROBABILISTIC SAFETY ASSESSMENT PSA IN DAYA BAY NUCLEAR POWER STATION
18th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18) Beijing, China, August 7-12, 2005 SMiRT18-A01-2 DEVELOPMENT AND APPLICATION OF PROBABILISTIC SAFETY ASSESSMENT PSA
More informationDraft Design Safety Requirements for Proposed Nigeria NPPs to SMRs and probable Application Challenges G. O. Omeje
Draft Design Safety Requirements for Proposed Nigeria NPPs to SMRs and probable Application Challenges G. O. Omeje TM on Challenges in the application of Design Safety Requirements for NPPs to SMRs 4th
More informationProspects of Nuclear Power Industry with Sodium-Cooled Fast Reactors
XI International Public Dialogue Forum NUCLEAR ENERGY, ENVIRONMENT, SAFETY 2016 Prospects of Nuclear Power Industry with Sodium-Cooled Fast Reactors B.A. Vasilyev Chief Designer of BN Reactor Plants November
More informationPSA ANALYSIS FOCUSED ON MOCHOVCE NPP SAFETY MEASURES EVALUATION FROM OPERATIONAL SAFETY POINT OF VIEW
International Conference Nuclear Energy in Central Europe 2001 Hoteli Bernardin, Portorož, Slovenia, September 10-13, 2001 www: http://www.drustvo-js.si/port2001/ e-mail: PORT2001@ijs.si tel.:+ 386 1 588
More informationGE Hitachi's ABWR and ESBWR: safer, simpler, smarter
GE Hitachi's ABWR and ESBWR: safer, simpler, smarter OECD/NEA Workshop on innovations in water-cooled reactor technologies Issy-les-Moulineaux, Paris 11-12 February, 2015 David Powell Vice President Nuclear
More informationEPRI Utility Requirement Document
EPRI Utility Requirement Document 11 February 2015 Sang-Baik KIM Analyst, NEA NDD Overview of URD Background and Objectives - Purpose of the URD is to present a clear, comprehensive set of design requirements
More informationAccident Management Programme for Indian Pressurized Heavy Water Reactors Chander Mohan Bhatia Nuclear Power Corporation of India Limited
Accident Management Programme for Indian Pressurized Heavy Water Reactors Chander Mohan Bhatia Nuclear Power Corporation of India Limited cmbhatia@npcil.co.in Presentation Contents Indian nuclear power
More informationThe Nuclear Landscape A Snapshot of the Global Issues and Players
American Association for the Advancement of Science Annual Meeting February 12th 16th, 2009, Chicago Keeping the Lights on the Revival of Nuclear Energy for our Future The Nuclear Landscape A Snapshot
More informationOur Contribution to the Forum
Our Contribution to the Forum General presentation of the EPR TM Reactor CR1.1.1 Robustness PART 1 Margins - Simplicity PART 2 Quality of design and construction Quality of materials Redundancy PART 3
More informationSAM strategy&modifications and SA simulator at Paks NPP
Technical Meeting on Verification and Validation of SAMGs for Nuclear Power Plants 12-14 December 2016, Vienna, Austria SAM strategy&modifications and SA simulator at Paks NPP Éva Tóth Group Leader Safety
More information