Preparedness at PFBR Kalpakkam to meet the challenges due to Natural events Prabhat Kumar, Project Director, PFBR, Director construction BHAVINI
|
|
- Laureen Glenn
- 6 years ago
- Views:
Transcription
1 BHARATIYA NABHIKIYA VIDYUT NIGAM LIMITED (A Government of India Enterprise) Preparedness at PFBR Kalpakkam to meet the challenges due to Natural events Prabhat Kumar, Project Director, PFBR, Director construction BHAVINI
2 PFBR REACTOR ASSEMBLY Item 1 Main Vessel 2 Core Support Structure 3 Core Catcher 4 Grid Plate 5 Core 6 Inner vessel 7 Roof slab 8 Large Rotatable Plug 9 Small Rotatable Plug 10 Control Plug 11 Absorber Rod Drive Mechanism 12 Transfer Arm 13 Intermediate Heat Exchanger 14 Primary Sodium Pump 15 Safety Vessel 16 Reactor Vault
3 PFBR Details No. of fuel Assemblies : 181 No. of pins in one Sub Assembly : :217 Refueling interval Pu enrichment Zone I/II Rx Coolant inlet /outlet : 185 EFPD : 20.7 / 27.7 wt % : 397 / 547 ºC Steam Temp. / Pressure : 490 ºC / 167 Kg/Cm 2
4 PFBR Flow Sheet
5 PFBR PFBR is being constructed near the coast of Bay of Bengal. Task Force has been constituted to review the issues related to the: safety of reactor, spent fuel storage facility Multiunit site and other related issues arising due to natural events.
6 Issues Public perception is very low Equipment failure Human error Matural Event
7 Public is affected Livelyhood Fear of new issue: Design? QA? Materials? Manufacturing? Terrorism? Insider Threat?-Even operator must not be able to damage the core
8 Public is not concerned of source of electricity- Several decades of effort of nuclear technology development is at risk if we can not win public confidence
9 Site Coastel- What if flooded due to cyclone Height of water during tsunami Effect of splash due to tsunami; Equipment Drainage
10 To be taken care Reactor Shutdown, maintaining core cooling and containment integrity Gravity drop Cooling in every scenario: Operational Grade Decay Heat Removal (OGDHR) 4 loops are provided, each loop having capacity of 8 MWTh. (Total decay heat 20 MWTh)
11 Safety assessment of external events leading to BDBA conditions to review and address the following parameters / issues : Capability for reactor shut down, maintaining shut down condition and core cooling Capability to maintain containment integrity under credible BDBA conditions
12 Review of DBA and BDBA conditions to assess the strengthening / upgradation of the systems required to ensure the containment integrity. Provision of reactor trip on seismic event
13 Guard pipe is provided around primary sodium piping Leak collection trays are provided for the secondary sodium piping. All pipe lines are of welded construction- No valves in primary main circuit Sodium fire fighting system is established
14 Support Systems Alernate Battery bank Spares Obstruction clearence Communication Large scale public movement Shelters
15 Storage of large quantity of Sodium in the Primary and Secondary systems Whether SGB could get flooded Can Sea water enter and affect the SS Whether fire fighting system is adequate Whether Cables have joints that can get affected Whether Adequate diesel supply can be ensured Water sources Can servive water, raw water and DM water get affected due to sea water ingress?
16 Spent fuel Storage Review of the spent fuel storage pool for seismic event higher than the design value. Review of possible cracks due to higher seismic, possible pipe line failure and provisions to make up the water level. Review of any possible fall of heavy object on storage pool during the seismic event.
17 Spent fuel Storage Spent fuel is kept in the spent fuel storage location in the reactor core for about two cycles. Hence decay heat of the spent fuel will be less when it is removed for storage in spent fuel storage pool. 45,000 Litres capacity demineralised water storage tank installed in the Fuel Building can supply water to spent fuel storage bay in case of failure of normal source. Yet provision planned for additional cooning facility
18 Effect on Spent Fuel and Fresh Fuel assemblies storage facilities to remain intact Analysis Water supply possibility
19 Availability of Diesel Generator beyond design basis scenario Possibility of hooking up back-up power supply system in the event of plant Diesel Generator unavailable Availability of Emergency Diesel Generators on wheel/ provision of backup power supply- Levels and Roads
20 Accident management strategy Emergency preparedness Emergency Crew Adequacy of the approaches to the plant site to handle emergency scenarios Accident management (site & off site-ndma, NDRF)
21 Preliminary review has indicated that we donot have much concern- many concerns were addressed after 2004 tsunami
22 PFBR plant is designed to be safe in all natural eventualities such as tsunami, earthquake, cyclone & flood. Kalpakkam comes in Seismic Category Zone III as per the seismic classification.
23 For PFBR, the Design Basis Flood Level is fixed as 6.45 metres above Mean Sea Level (MSL) based on 1000 years return period During the worst ever Tsunami that stuck Kalpakkam in Dec. 2004, the maximum water level rise was 4.71 metres above MSL.
24 After the Tsunami at Kalpakkam in Dec. 2004, shore protection and Tsunami bund made out of engineered boulders stacked at a height of 5.4 Meters above MSL was erected for breaking the intensity of sea waves during tsunami.
25 Shore protection Tsunami bund 25
26 The finished floor level of Safety related Buildings are at metres above Mean Sea Level (MSL) :
27 The finished floor levels of Safety related Buildings are 3.15 metres above Design Basis Flood Level (6.45M)and 4.9 metres above the maximum water level rise observed during Tsunami in Dec (4.71 M)) Hence operation of Emergency Diesel Generators, reactor safe shut down & cooling and spent fuel cooling will not be affected during a design basis Tsunami event.
28 Hydrogen Issue In PFBR water is not used as the coolant for reactor. This precludes any possibility of hydrogen generation/explosion in RCB. Fuel clad material is not Zirconium (it is Alloy D-9 an alloy of Cr, Ni, Mo, Ti & Si). Hence no metal water reaction & hydrogen generation in Spent fuel storage facility in case loss of cooling. However Hydrogen due to BSC water and sodium need to be studied
29 Emergency Diesel Power PFBR is provided with four diesel generators Two are sufficient to meet the station requirement All four DGs are in separate buildings 2 are in east. Remaining 2 are in the west side of Main plant building, away from sea side. Located at meters above MSL
30 An in-depth study by the Task Force is in progress to review & identify any weakness Based on the review and recommendations of Task Force, modifications will be carried out to address these issues.
31 Erection of steam generator
32
33
34 Mock up work completed as per the guide lines of PDSC. Welding commenced
35 Sea water Intake 1. Sinking of caisson has reached beyond soft rock region. 2. Concreting of caisson completed for 12 m depth from cutting edge. 3. Inside caisson chiseling and grabbing work is in progress. 4. On top of jetty pipe line pedestal work is in progress.
36 Major TG equipment's at site Around 4000 Tons of material reached site in TG package
37 Thank you
DESIGN AND FABRICATION OF SERPENTINE TUBE TYPE SODIUM TO AIR HEAT EXCHANGERS FOR PFBR SGDHR CIRCUITS
DESIGN AND FABRICATION OF SERPENTINE TUBE TYPE SODIUM TO AIR HEAT EXCHANGERS FOR PFBR SGDHR CIRCUITS Aravinda Pai, T.K.Mitra, T. Loganathan and Prabhat Kumar Prototype Fast Breeder Reactor Project Bharatiya
More informationPost-Fukushima Assessment of the AP1000 Plant
ABSTRACT Post-Fukushima Assessment of the AP1000 Plant Ernesto Boronat de Ferrater Westinghouse Electric Company, LLC Padilla 17-3 Planta 28006, Madrid, Spain boronae@westinghouse.com Bryan N. Friedman,
More informationThe 2011 Tohoku Pacific Earthquake and Current Status of Nuclear Power Stations
The 2011 Tohoku Pacific Earthquake and Current Status of Nuclear Power Stations March 31, 2011 Tokyo Electric Power Company Tohoku Pacific Ocean Earthquake Time: 2:46 pm on Fri, March 11, 2011. Place:
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 informationProceedings of the National Seminar & Exhibition on Non-Destructive Evaluation. NDE 2011, December 8-10, 2011
Proceedings of the National Seminar & Exhibition on Non-Destructive Evaluation NDE 2011, December 8-10, 2011 QUALITY CONTROL & QUALITY ASSURANCE FOR TUBE TO TUBESHEET JOINTS AND SHELL WELD JOINTS OF STRAIGHT
More informationFrequently Asked Questions: Japanese Nuclear Energy Situation
NUCLEAR ENERGY INSTITUTE Frequently Asked Questions: Japanese Nuclear Energy Situation 1. What will be the impact of the Fukushima Daiichi accident on the U.S. nuclear program? It is premature to draw
More informationIsolation Condenser; water evaporation in the tank and steam into the air. Atmosphere (in Severe Accident Management, both P/S and M/S)
Loss of Ultimate Heat Sink ANS AESJ AESJ Fukushima Symposium, March h4, 2012 Hisashi Ninokata, Tokyo Institute of Technology Available ultimate heat sinks at 1F1~3 1F1 (Fukushima Dai ichi Unit 1) Sea water
More informationFOSH Forsmark Safety Enhancement Project Post-Fukushima actions at Forsmark NPP
FOSH Forsmark Safety Enhancement Project Post-Fukushima actions at Forsmark NPP NKS January 12-13, 2016 Ove Nilsson Sekretessklass: Open (S1) 1 2015-12-23 FOSH Forsmark Safety Enhancement Project F-0003165
More informationCNE Cernavoda Response to Fukushima Event/EU Stress Test Requirements
CNE Cernavoda Response to Fukushima Event/EU Stress Test Requirements Sorin Holostencu IAEA Technical Meeting on Operational Experience with Implementation of Post-Fukushima Actions in Nuclear Power Plants,
More informationEuropean level recommendations Sect. in NAcP 2 Generic recommendation for WENRA, Finland participates and follows the work.
Cross reference table of ENSREG and Extraordinary CNS recommendations and national actions 1(16) 2.1 European guidance on assessment of natural hazards and margins The peer review Board recommends that
More informationBrazilian Operator s Response to Fukushima Daiichi Accident Luiz Soares Technical Director
Simposyum Siting of New Nuclear Power Plants and Irradiated Fuel Facilities Buenos Aires Argentina 24-28 June 2013 Panel Fukushima Daiichi s Impact in Nuclear Power Programs Worldwide Brazilian Operator
More informationNeutron Flux Monitoring System in Prototype Fast Breeder Reactor
Neutron Flux Monitoring System in Prototype Fast Breeder Reactor M.Sivaramakrishna, C.P. Nagaraj, K. Madhusoodanan, Dr. P. Chellapandi Indira Gandhi Centre For Atomic Research, Kalpakkam, Tamilnadu Abstract
More informationLessons Learned from Fukushima Daiichi Nuclear Power Station Accident and Consequent Safety Improvements
Hitachi Review Vol. 62 (2013), No. 1 75 Lessons Learned from Fukushima Daiichi Nuclear Power Station Accident and Consequent Safety Improvements Masayoshi Matsuura Kohei Hisamochi Shinichiro Sato Kumiaki
More informationEnhancement of Nuclear Safety
Enhancement of Nuclear Safety Soon Heung Chang Handong Global University May 6, 2015 Contents 1 2 3 4 Importance of Energy Fundamentals of Nuclear Safety How to Enhance Nuclear Safety Closing Remarks 2
More informationWestinghouse Small Modular Reactor. Passive Safety System Response to Postulated Events
Westinghouse Small Modular Reactor Passive Safety System Response to Postulated Events Matthew C. Smith Dr. Richard F. Wright Westinghouse Electric Company Westinghouse Electric Company 600 Cranberry Woods
More informationSystem Analysis of Pb-Bi Cooled Fast Reactor PEACER
OE-INES-1 International Symposium on Innovative Nuclear Energy Systems for Sustainable Development of the World Tokyo, Japan, October 31 - November 4, 2004 System Analysis of Pb-Bi ooled Fast Reactor PEAER
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 informationSmall Modular Reactors: A Call for Action
Small Modular Reactors: A Call for Action Overview of Five SMR Designs by Dr. Regis A. Matzie Executive Consultant Adapted May 2015 for the Hoover Institution's Reinventing Nuclear Power project from a
More informationReactor Technology: Materials, Fuel and Safety. Dr. Tony Williams
Reactor Technology: Materials, Fuel and Safety Dr. Tony Williams Course Structure Unit 1: Reactor materials Unit 2. Reactor types Unit 3: Health physics, Dosimetry Unit 4: Reactor safety Unit 5: Nuclear
More informationThe Westinghouse Advanced Passive Pressurized Water Reactor, AP1000 TM. Roger Schène Director,Engineering Services
The Westinghouse Advanced Passive Pressurized Water Reactor, AP1000 TM Roger Schène Director,Engineering Services 1 Background Late 80: USA Utilities under direction of EPRI and endorsed by NRC : Advanced
More informationANTARES Application for Cogeneration. Oil Recovery from Bitumen and Upgrading
ANTARES Application for Cogeneration Oil Recovery from Bitumen and Upgrading Michel Lecomte Houria Younsi (ENSEM) Jérome Gosset (ENSMP) ENC Conference Versailles 11-14 December 2005 1 Presentation Outline
More informationDesign Safety Considerations for Water-cooled Small Modular Reactors As reported in IAEA-TECDOC-1785, published in March 2016
International Conference on Topical Issues in Nuclear Installation Safety, Safety Demonstration of Advanced Water Cooled Nuclear Power Plants 6 9 June 2017 Design Safety Considerations for Water-cooled
More informationACR-1000: ENHANCED RESPONSE TO SEVERE ACCIDENTS
ACR-1000: ENHANCED RESPONSE TO SEVERE ACCIDENTS Popov, N.K., Santamaura, P., Shapiro, H. and Snell, V.G Atomic Energy of Canada Limited 2251 Speakman Drive, Mississauga, Ontario, Canada L5K 1B2 1. INTRODUCTION
More informationRegulatory Guide Monitoring the Effectiveness of Maintenance at Nuclear Power Plants
Regulatory Guide 1.160 Revision 2 Page 1 of 14 Revision 2 March 1997 Regulatory Guide 1.160 Monitoring the Effectiveness of Maintenance at Nuclear Power Plants Publication Information (Draft issued as
More informationAP1000 European 19. Probabilistic Risk Assessment Design Control Document
19.39 In-Vessel Retention of Molten Core Debris 19.39.1 Introduction In-vessel retention of molten core debris through water cooling of the external surface of the reactor vessel is a severe accident management
More informationCLASSIFICATION OF SYSTEMS, STRUCTURES AND COMPONENTS OF A NUCLEAR FACILITY
CLASSIFICATION OF SYSTEMS, STRUCTURES AND COMPONENTS OF A NUCLEAR FACILITY 1 Introduction 3 2 Scope of application 3 3 Classification requirements 3 3.1 Principles of safety classification 3 3.2 Classification
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 informationIV. Occurrence and Development of the Accident at the Fukushima Nuclear Power Stations
IV. Occurrence and Development of the Accident at the Fukushima Nuclear Power Stations 1. Outline of Fukushima Nuclear Power Stations (1) Fukushima Daiichi Nuclear Power Station Fukushima Daiichi Nuclear
More informationStatus of the FRM-II Project at Garching. Hans-Jürgen Didier, Gunter Wierheim Siemens AG, Power Generation (KWU), D Erlangen
IGORR7 7 th Meeting of the International Group on Research Reactors October 26-29, 1999 Bariloche, Argentina Status of the FRM-II Project at Garching Hans-Jürgen Didier, Gunter Wierheim Siemens AG, Power
More informationCurrent Status of Research and Development on System Integration Technology for Connection between HTGR and Hydrogen Production System at JAEA
Current Status of Research and Development on System Integration Technology for Connection between HTGR and Hydrogen Production System at JAEA Hirofumi Ohashi, Yoshitomo Inaba, Tetsuo Nishihara, Tetsuaki
More informationEvolution of Nuclear Energy Systems
ALLEGRO Project 2 Evolution of Nuclear Energy Systems 3 General objectives Gas cooled fast reactors (GFR) represent one of the three European candidate fast reactor types. Allegro Gas Fast Reactor (GFR)
More informationIn April 1986, unit 4 of the Chernobyl nuclear
Safety of RBMK reactors: Setting the technical framework The IAEA's co-operative programme is consolidating the technical basis for further upgrading the safety of Chernobyl-type reactors by Luis Lederman
More informationNuScale SMR Technology
NuScale SMR Technology UK IN SMR; SMR IN UK Conference - Manchester, UK Tom Mundy, EVP Program Development September 25, 2014 Acknowledgement & Disclaimer This material is based upon work supported by
More informationNuclear Reactor Types. An Environment & Energy FactFile provided by the IEE. Nuclear Reactor Types
Nuclear Reactor Types An Environment & Energy FactFile provided by the IEE Nuclear Reactor Types Published by The Institution of Electrical Engineers Savoy Place London WC2R 0BL November 1993 This edition
More informationThe ESBWR an advanced Passive LWR
1 IAEA PC-Based Simulators Workshop Politecnico di Milano, 3-14 October 2011 The ES an advanced Passive LWR Prof. George Yadigaroglu, em. ETH-Zurich and ASCOMP yadi@ethz.ch 2 Removal of decay heat from
More informationOperatiOn and safety report Of MOchOvce and BOhunice v2 nuclear power plants
2016 OperatiOn and safety report Of MOchOvce and BOhunice v2 nuclear power plants The company is certified according to three management systems: Certificate stn en iso 9001:2008 Quality management system
More informationSAFETY GUIDES. Deterministic Safety Assessment РР - 5/2010 ÀÃÅÍÖÈß ÇÀ ßÄÐÅÍÎ ÐÅÃÓËÈÐÀÍÅ BULGARIAN NUCLEAR REGULATORY AGENCY
S ON IMPLEMENTATION OF THE LEGAL REQUIREMENTS Deterministic Safety Assessment РР - 5/2010 ÀÃÅÍÖÈß ÇÀ ßÄÐÅÍÎ ÐÅÃÓËÈÐÀÍÅ BULGARIAN NUCLEAR REGULATORY AGENCY TABLE OF CONTENTS 1. GENERAL PROVISIONS...2 LEGAL
More informationModule 05 WWER/ VVER (Russian designed Pressurized Water Reactors)
Module 05 WWER/ VVER (Russian designed Pressurized Water Reactors) 1.3.2016 Prof.Dr. Böck Technical University Vienna Atominstitut Stadionallee 2, 1020 Vienna, Austria ph: ++43-1-58801 141368 boeck@ati.ac.at
More informationContents of summary. 1. Introduction
Contents of summary 1. Introduction 2. Situation regarding Nuclear Safety Regulations and Other Regulatory Frameworks in Japan before the Accident 3. Disaster Damage in Japan from the Tohoku District -
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 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 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 informationPost-Fukushima Action Plan in Korea. WNU-SI 2011, August 11 Christ Church, Oxford
Post-Fukushima Action Plan in Korea WNU-SI 2011, August 11 Christ Church, Oxford Contents Korean nuclear overview BK Kim Government action plan BS Jeong Post-Fukushima action plan MK Jo Nuclear Power Plants
More informationOPG Proprietary Report
N/A R001 2 of 114 Table of Contents Page List of Tables and Figures... 5 Revision Summary... 6 Executive Summary... 7 1.0 INTRODUCTION... 9 1.1 Objectives... 10 1.2 Scope... 10 1.3 Organization of Summary...
More informationRESULTS OF THE GRADUAL UPGRADING AT BOHUNICE WWER - 440/230 NPP
RESULTS OF THE GRADUAL UPGRADING AT BOHUNICE WWER - 440/230 NPP P. Krupa Ingeneer, e-mail: Krupa_Peter@ebo.seas.sk Bohunice NPPs Introduction The centre of upgrading activities in VVER NPP is clearly in
More informationMeasures against Earthquakes and Tsunamis in View of the Accident at Fukushima Daiichi Nuclear Power Station
Nuclear and Industrial Safety Agency Ministry of Economy, Trade and Industry IEM 3: International Expert s Meeting (Earthquakes / Tsunamis) 4-7 September, 2012 Vienna Measures against Earthquakes and Tsunamis
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 informationGorgon Project Update: Selected Images
Gorgon Project Update: Selected Images September 25, 2012 Plant Site Construction of the liquefied natural gas (LNG) plant is progressing well. Once complete, the plant will comprise three trains capable
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 informationExperiments Carried-out, in Progress and Planned at the HTR-10 Reactor
Experiments Carried-out, in Progress and Planned at the HTR-10 Reactor Yuliang SUN Institute of Nuclear and New Energy Technology, Tsinghua University Beijing 100084, PR China 1 st Workshop on PBMR Coupled
More informationPakistan s Experience in Operating CNP-300s and Near Term Deployment Scheme
Pakistan s Experience in Operating CNP-300s and Near Term Deployment Scheme Presented by: M. Kamran Chughtai Directorate of Nuclear Power Engineering Reactor PAKISTAN ATOMIC ENERGY COMMISSION IAEA Work
More informationFRANCE LWR activities
FRANCE LWR activities Norbert NICAISE with contributions from AREVA-NP ASN French Nuclear Safety Authority, IRSN French Institute for Radiation Protection and Nuclear Safety (TSO of ASN), CEA French Atomic
More informationRELAP 5 ANALYSIS OF PACTEL PRIMARY-TO-SECONDARY LEAKAGE EXPERIMENT PSL-07
Fifth International Seminar on Horizontal Steam Generators 22 March 21, Lappeenranta, Finland. 5 ANALYSIS OF PACTEL PRIMARY-TO-SECONDARY LEAKAGE EXPERIMENT PSL-7 József Bánáti Lappeenranta University of
More informationSpecification for Phase VII Benchmark
Specification for Phase VII Benchmark UO 2 Fuel: Study of spent fuel compositions for long-term disposal John C. Wagner and Georgeta Radulescu (ORNL, USA) November, 2008 1. Introduction The concept of
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 informationDecommissioning Group Ketut Kamajaya
Decommissioning Group Ketut Kamajaya Contents of presentation Briefly history of Bandung TRIGA reactor Location of the facility Decommissioning options Characterization of System, Structure and Component
More informationRELAP5/MOD3.2 INVESTIGATION OF A VVER-440 STEAM GENERATOR HEADER COVER LIFTING
Science and Technology Journal of BgNS, Vol. 8, 1, September 2003, ISSN 1310-8727 RELAP5/MOD3.2 INVESTIGATION OF A VVER-440 STEAM GENERATOR HEADER COVER LIFTING Pavlin P. Groudev, Rositsa V. Gencheva,
More informationEXPERIMENTS ON THE PERFORMANCE SENSITIVITY OF THE PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF AN ADVANCED INTEGRAL TYPE REACTOR
EXPERIMENTS ON THE PERFORMANCE SENSITIVITY OF THE PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF AN ADVANCED INTEGRAL TYPE REACTOR HYUN-SIK PARK *, KI-YONG CHOI, SEOK CHO, SUNG-JAE YI, CHOON-KYUNG PARK and MOON-KI
More informationCOUPLING A HYDROGEN PRODUCTION PROCESS TO A NUCLEAR REACTOR
COUPLING A HYDROGEN PRODUCTION PROCESS TO A NUCLEAR REACTOR P. Anzieu, P. Aujollet, D. Barbier, A. Bassi, F. Bertrand, A. Le Duigou, J. Leybros, G. Rodriguez CEA, France NEA 3 rd Meeting on Nuclear Production
More informationWestinghouse s plant for the Nuclear Renaissance : AP1000. AP1000 Advanced Passive Plant
Westinghouse s plant for the Nuclear Renaissance : AP000 Fernando Naredo Milan, January 30, 006 AP000 Advanced Passive Plant Designed to compete with other sources in deregulated power markets - Two loop,
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 informationJournal of American Science 2014;10(2) Burn-up credit in criticality safety of PWR spent fuel.
Burn-up credit in criticality safety of PWR spent fuel Rowayda F. Mahmoud 1, Mohamed K.Shaat 2, M. E. Nagy 3, S. A. Agamy 3 and Adel A. Abdelrahman 1 1 Metallurgy Department, Nuclear Research Center, Atomic
More informationABSTRACT. The Guidelines Section C is related to the classification and grading approach of NSQ100 (Chapters & 4.1.3).
Page 1 / 11 ABSTRACT This document is the Section C to NSQ-100 Guidelines. Its objective is to help to the understanding of NSQ-100 requirements through some examples or recommendations and descriptions
More informationRadioactive Waste Management at the NCSR Demokritos - Greece
Radioactive Waste Management at the NCSR Demokritos - Greece Anastasia Savidou Radioactive Materials Management Laboratory Institute of Nuclear & Radiological Sciences & Technology, Energy & Safety, National
More informationInternational Atomic Energy Agency. Impact of Extreme Events on Nuclear Facilities following Fukushima. Dr C H Shepherd Nuclear Safety Consultant, UK
Impact of Extreme Events on Nuclear Facilities following Fukushima by Dr C H Shepherd Nuclear Safety Consultant, UK CRA PSA/HFA Forum 8-9 September 2011, Warrington Contents of the Presentation IAEA views
More informationModule 11 Liquid Metal Fast Breeder Reactors (LMFBR) Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria
Module 11 Liquid Metal Fast Breeder Reactors (LMFBR) Prof.Dr. H. Böck Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria boeck@ati.ac.at LMFBR Basics A fast breeder reactor
More informationRecent Approaches related to Safety Enhancement of Operating NPPs in Korea Tae Eun JIN KEPCO E&C
Int. Conf. on Topical Issues in Nuclear Installation Safety, Vienna Austria, 6~9 Jun. 2017 Recent Approaches related to Safety Enhancement of Operating NPPs in Korea Tae Eun JIN KEPCO E&C Contents 1. Introduction
More informationVincent Rebour, Frédéric Ménage IRSN: PRP-DGE/SCAN, PSN-EXP. Assessing flooding hazards: new guidelines
Vincent Rebour, Frédéric Ménage IRSN: PRP-DGE/SCAN, PSN-EXP Assessing flooding hazards: new guidelines 1 Content 1. Experience feedback from Le Blayais 2. New guidelines for NPPs and other NIs 3. Conclusion
More informationOPG Proprietary Report
N/A R001 2 of 121 Table of Contents Page List of Tables and Figures... 5 Revision Summary... 6 Executive Summary... 7 1.0 INTRODUCTION... 9 1.1 Objectives... 10 1.2 Scope... 10 1.3 Organization of Summary...
More informationANTARES The AREVA HTR-VHTR Design PL A N TS
PL A N TS ANTARES The AREVA HTR-VHTR Design The world leader in nuclear power plant design and construction powers the development of a new generation of nuclear plant German Test facility for HTR Materials
More informationAPR1400 Safe, Reliable Technology
APR1400 Safe, Reliable Technology OECD/NEA Workshop on Innovations in Water-cooled Reactor Technology Paris, Feb 11 12, 2015 Presented by Shin Whan Kim Contents 1. Introduction 2. Major Safety Design Characteristics
More informationDevelopment and use of SAMGs in the Krško NPP
REPUBLIC OF SLOVENIA Development and use of SAMGs in the Krško NPP Tomaž Nemec Slovenian Nuclear Safety Administration tomaz.nemec@gov.si IAEA TM on the Verification and Validation of SAMGs, Vienna, 12
More informationSPENT FUEL STORAGE IN BELGIUM
SPENT FUEL STORAGE IN BELGIUM R. Vermeyen Tractebel Energy Engineering Belgatom 1. Introduction The Belgian utility Electrabel presently operates 7 PWR nuclear power plants, distributed over two sites
More informationACCIDENT PREVENTION & EMERGENCY RESPONSE
Attachment J ACCIDENT PREVENTION & EMERGENCY RESPONSE Cadbury Ireland Limited Project Ref: OES1061_01 Cadbury Ireland Limited February 2007 Attachment J J.1 Accidental Emissions Control Accidental emissions
More informationModule 06 Boiling Water Reactors (BWR)
Module 06 Boiling Water Reactors (BWR) 1.10.2015 Prof.Dr. Böck Vienna University oftechnology Atominstitute Stadionallee 2 A-1020 Vienna, Austria ph: ++43-1-58801 141368 boeck@ati.ac.at Contents BWR Basics
More informationThe DENOPI project: a research program on SFP under loss-of-cooling and loss-of-coolant accident conditions
The DENOPI project: a research program on SFP under loss-of-cooling and loss-of-coolant accident conditions NAS meeting March 2015 N. Trégourès, H. Mutelle, C. Duriez, S. Tillard IRSN / Nuclear Safety
More informationStainless Steel Pressure Vessels, Process Vessels and Tanks. Examples of manufactured products
Stainless Steel Pressure Vessels, Process Vessels and Tanks Examples of manufactured products Siljan Allards AB www.siljanallards.com Page 1 To the right, one out of six process vessels, installed in a
More informationApparel Gallery Ltd.
Apparel Gallery Ltd. 147-148, Norshinghpur, Asulia, Savar, Dhaka (23.929985N,90.304914E) 23 March 2014 1 2 Observations Building 1 Heavy loading due to raised floor area on Ground Floor 3 Building 1 Raised
More informationSwedish action plan. for nuclear power plants
Swedish action plan for nuclear power plants Response to ENSREG s request December 2012 Page 2 (48) Abstract Following the severe accidents which started in the Fukushima Dai-ichi nuclear power plant,
More informationINL/EXT Key Design Requirements for the High Temperature Gascooled Reactor Nuclear Heat Supply System
INL/EXT-10-19887 Key Design Requirements for the High Temperature Gascooled Reactor Nuclear Heat Supply System September 2010 DISCLAIMER This information was prepared as an account of work sponsored by
More informationPHENIX AND SUPERPHENIX FEEDBACK EXPERIENCE. GUIDEZ Joel C E A / France
PHENIX AND SUPERPHENIX FEEDBACK EXPERIENCE GUIDEZ Joel C E A / France Meet the presenter Joël Guidez began his career in the field of sodium-cooled fast reactors, after graduating from the Ecole Centrale
More informationNUCLEAR ENERGY MATERIALS AND REACTORS - Vol. II - Advanced Gas Cooled Reactors - Tim McKeen
ADVANCED GAS COOLED REACTORS Tim McKeen ADI Limited, Fredericton, Canada Keywords: Advanced Gas Cooled Reactors, Reactor Core, Fuel Elements, Control Rods Contents 1. Introduction 1.1. Magnox Reactors
More informationThe Fukushima Nuclear Accident: Insights on the Safety Aspects
World Journal of Nuclear Science and Technology, 2015, 5, 169-182 Published Online July 2015 in SciRes. http://www.scirp.org/journal/wjnst http://dx.doi.org/10.4236/wjnst.2015.53017 The Fukushima Nuclear
More informationEVALUATION OF A CHEMICAL CLEANING FORMULATION FOR THE STEAM GENERATOR OF NUCLEAR POWER PLANTS
EVALUATION OF A CHEMICAL CLEANING FORMULATION FOR THE STEAM GENERATOR OF NUCLEAR POWER PLANTS A.L.Rufus, H.Subramanian, V.S.Sathyaseelan, Padma S.Kumar, S.Veena B.Anupkumar, M.P.Srinivasan, S.Velmurugan
More informationMIT NUCLEAR REACTOR LABORATORY. Technical Analysis and Administrative Issues of Criticality Study for Different MITR Facilities
MIT NUCLEAR REACTOR LABORATORY an MIT Interdepartmental Center Technical Analysis and Administrative Issues of Criticality Study for Different MITR Facilities Kaichao Sun, MIT-NRL Group Leader Reactor
More informationGUIDELINES FOR REGULATORY REVIEW OF EOPs AND SAMGs
GUIDELINES FOR REGULATORY REVIEW OF EOPs AND SAMGs CNCAN, ROMANIA 2016 1 TABLE OF CONTENTS 1. INTRODUCTION 1.1. Background 1.2. Purpose and scope of the guidelines 1.3. Structure of the guidelines 1.4.
More informationMajor Influential Issues on the Accident Progressions of Fukushima Daiichi NPP
1/12 Major Influential Issues on the Accident Progressions of Fukushima Daiichi NPP Summary M. Naitoh, M. Pellegrini. H. Suzuki, H. Mizouchi, and H. Okada The Institute of Applied Energy, Japan This paper
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 informationEnsuring Spent Fuel Pool Safety
Ensuring Spent Fuel Pool Safety Michael Weber Deputy Executive Director for Operations U.S. Nuclear Regulatory Commission American Nuclear Society Meeting June 28, 2011 1 Insights from Fukushima Nuclear
More informationNPP Simulators Workshop for Education - Passive PWR NPP & Simulator Overview
NPP Simulators Workshop for Education - Passive PWR NPP & Simulator Overview Wilson Lam (wilson@cti-simulation.com) CTI Simulation International Corp. www.cti-simulation.com Sponsored by IAEA Modified
More informationTHE ROLE OF THE WORLD'S LARGEST INTERIM STORAGE FOR WASTE AND FUEL WITHIN THE DECOM PROJECT OF 6 WWER REACTORS IN GREIFSWALD AND RHEINSBERG (GERMANY)
THE ROLE OF THE WORLD'S LARGEST INTERIM STORAGE FOR WASTE AND FUEL WITHIN THE DECOM PROJECT OF 6 WWER REACTORS IN GREIFSWALD AND RHEINSBERG (GERMANY) Hartmann, Burkhard Leushacke, Dieter F. Dr Energiewerke
More informationEPR: Steam Generator Tube Rupture analysis in Finland and in France
EPR: Steam Generator Tube Rupture analysis in Finland and in France S. ISRAEL Institut de Radioprotection et de Sureté Nucléaire BP 17 92262 Fontenay-aux-Roses Cedex, France Abstract: Different requirements
More informationTraining Certification Categories
Training Certification Categories Residential Residential Building Inspector structures are free from hazardous structural conditions and comply with the UCC. Duties include inspection of footings and
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 informationWM2014 Conference, March 2 6, 2014, Phoenix, Arizona, USA
Integrity Study of Spent PWR Fuel under Dry Storage Conditions 14236 Jongwon Choi *, Young-Chul Choi *, Dong-Hak Kook * * Korea Atomic Energy Research Institute ABSTRACT Technical issues related to long-term
More informationNuclear Reactor Types
http://www.theiet.org/cpd Nuclear Reactor Types This Factfile summarises the main designs for nuclear reactors around the world. www.theiet.org/factfiles Nuclear Reactor Types Many different reactor systems
More informationHTGR Brayton Cycle Technology and Operations
MIT Workshop on New Cross-cutting Technologies for Nuclear Power Plants, Cambridge, USA, January 30-3, 207 HTGR Brayton Cycle Technology and Operations Xing L. Yan HTGR Hydrogen and Heat Application Research
More informationSTORAGE OF SPENT NUCLEAR FUEL IN MVDS OF PAKS NPP
Technical section STORAGE OF SPENT NUCLEAR FUEL IN MVDS OF PAKS NPP Zoltán Huszák, János Bencze Fuel Handling Machine Operator Paks NPP, Hungary 1. INTRODUCTION Four VVER-440/213 type reactors operate
More informationThe Accident at Fukushima: What Happened?
The Accident at Fukushima: What Happened? February 27, 2012 Takao Fujie President and Chief Executive Officer (JANTI) Copyright 2012. All Rights Reserved. The Accident at Fukushima: What Happened? Foreword
More information