Design Features, Economics and Licensing of the 4S Reactor
|
|
- Griffin Augustus Taylor
- 6 years ago
- Views:
Transcription
1 PSN Number: PSN Document Number: AFT rev.000(2) Design Features, Economics and Licensing of the 4S Reactor ANS Annual Meeting June 13 17, 2010 San Diego, California Toshiba Corporation: Y. Tsuboi, K. Arie Westinghouse: T. Grenci 1
2 Outline 1. 4S Key Features 2. Demonstration of Key Components 3. Economics 4. Licensing 5. Concluding Remarks 2/28
3 1. 4S Key Features 2. Demonstration of Key Components 3. Economics 4. Licensing 5. Concluding Remarks 3/28
4 4S (Super-Safe, Small & Simple) Sodium-cooled pool type fast reactor Versions 10 MWe (30MWt) 50 MWe (135MWt) Main features Refueling interval 10 MWe: 30 years 50 MWe: 10 years Passive safety Minimal moving parts Security and safeguards designed in R/B located below grade Reactor Turbine/ Generator Steam Generator Co-developer: CRIEPI Developing partners: ANL, WEC 4/28
5 No Refueling for 30 Years (10MWe-4S) Reflector controlled core with metallic fuel Long cylindrical core with small diameter Outer fuel Inner fuel Fuel pins Shutdown rod Core 2. 5m Fuel Fuel vol. frac. 50% Cladding 235 U enrichment (Inner/ Outer) Average Burnup U-10%Zr HT-9 17 / 19% 34,000 MWd/t Reflector Fixed absorber 5/28
6 Passive Decay Heat Removal Natural air draft & natural circulation RVACS : Natural air draft outside the guard vessel IRACS : Natural circulation of sodium and air draft at air cooler Air outlet Air outlet Air inlet IRACS (Air Cooler) Sodium flow Temperature ( ) Primary temperature(~260,000sec) Core-inlet Core-outlet Air inlet Guard Vessel RVACS SG , , , , ,000 Time (s) Core temperature during loss-of-power only with natural circulation Air flow pass RVACS: Reactor Vessel Auxiliary Cooling System, IRACS : Intermediate Reactor Auxiliary Cooling System 6/28
7 Low Maintenance Requirements Electromagnetic pump in primary system No rotating parts Immersed Type Iron core Coil Duct Sodium EM Pump 7/28
8 1. 4S Key Features 2. Demonstration of Key Components 3. Economics 4. Licensing 5. Concluding Remarks 8/28
9 Status of Verification Tests Design Feature Verification Item Required Testing Status Long cylindrical core with small diameter Reflector controlled core Nuclear design method of reflector controlled core with metallic fuel Critical experiment Done High volume fraction metallic fuel core Reflector RVACS Confirmation of pressure drop in fuel subassembly Reflector drive mechanism fine movement Heat transfer characteristics between vessel and air Fuel hydraulic test Test of reflector drive mechanism Heat transfer test of RVACS Done Ongoing Done EM pump/flowmeter Steam generator (Double wall tubes) Structural integrity Stable characteristics Structural integrity Heat transfer characteristics Leak detection Sodium test of EM pump/flowmeter Sodium test of steam generator Leak detection test Ongoing Ongoing Seismic isolation Applicability to nuclear plant Test of seismic isolator Done 9/28
10 Reflector Controlled Core Critical experiment for 4S core has been successfully performed. Shutdown rod Core Reflector Photo ; FCA (offered by JAEA) Reflector controlled core R&D has been performed by CRIEPI in collaboration with JAEA as a part of Innovative Nuclear Energy System Technology (INEST) Development Projects under sponsorship of MEXT (JAPAN). 10/28
11 Toshiba Sodium Test Loop Facility Max temperature Sodium inventory Sodium flow rate 600 o C 8 ton 0 12 m 3 /min 4S full-scale EM pump Mother loop area EM pump test area 11/28
12 Full-scale Test of EM Pump Toshiba Test Facility Full-scale EM Pump The performance of the EM pump has been demonstrated for the rated power condition of 4S in February, 2010 (This study is a part of Development of high temperature electromagnetic pump with large diameter and a passive flow coast compensation power supply to be adapted into medium and small reactors of GNEP funded by METI.) 12/28
13 Electromagnetic Flow-Meter magnetic core exciting coil electrode outer duct annular flow area channnel sodium inner duct Configuration of EMF Full sector test model Test Apparatus Sector test model Electromagnetic flow-meter (EMF) for 4S EM pump was fabricated, and will be tested using sodium this year. (This study is a part of Development of a new EMF in Sodium-cooled Fast Reactor funded by MEXT.) 13/28
14 Double Wall Steam Generator (DWSG) Double-wall helical coil type with 30 MWt capacity Inner tube leak detection Moisture detection in helium between inner and outer tubes Outer tube leak detection Helium detection in the intermediate sodium circuit Sodium flow Water flow Inner tube Wire mesh and helium Outer tube Development Study of a Wire Mesh Filled Double Wall Tube for FBR Steam Generators I.Ohshima et.al. Transactions of the Atomic Energy Society of Japan, Vol.36, Sodium No.9 (1994) 原子炉容器 14/28
15 DWSG Technology Manufacturing technologies of double-wall tube have been established in (funded by METI) Welded portion of inner tube Section view 10 meter-long double-wall tube with wire mesh Laser welding machine for inner tube Tube inspection technology has been established in Double-wall tube Indirect field Assumed defect Eddy current Direct field Small defect (1.0 mmφ) on outer tube surface has been successfully detected by Remote-Field Eddy Current Technology. Exciter coil Detector coil 15/28
16 Sodium Tests Schedule JFY2008 JFY2009 JFY2010 Pre-operation Na Test (Internal funding) EM flow meter Design and Fabrication (MEXT) Na Test (Internal funding) Design and Fabrication Installation Na Test 10.6m 3 /min EM pump (METI) Design and Fabrication Installation Na Test Reflector cavity Design and Fabrication Na Test (Internal funding) Key technologies for 4S will be established by the end of this fiscal year. 16/28
17 1. 4S Key Features 2. Demonstration of Key Components 3. Economics 4. Licensing 5. Concluding Remarks 17/28
18 Economics Target cost with mass production 10 MWe 4S : competitive with diesel power plant at remote area 50 MWe 4S : slightly higher than large LWRs To achieve the target, Reduce on-site construction work by shop fabrication Mass production Reduce O&M cost by low maintenance requirements Simplified spent fuel handling system by long refueling interval To reduce initial financial cost & risk, Small reactor Flexibility to meet increased demand by modular plant deployment scheme 18/28
19 Shop Fabrication Construction at site Reactor (Shop fabrication) Building (Shop fabrication) Steel concrete composite Site construction Barge Shop fabrication reduces site work and its duration 19/28
20 Modular Concept (example) Initial phase 1st unit 4S-135 MWt T/G Electricity Multiple phase shared auxiliary facilities 2nd unit 4S-135 MWt T/G Electricity Nth unit 4S-135 MWt T/G Electricity Low initial costs & risk Cost reduction by plant standardization and shared facilities for multiple phases 20/28
21 Fabrication Scheme Most of the components The technologies for most components are proven by the experience base for sodium-cooled fast reactors. These components will be procured from established vendors. 4S Specific components The key sodium components (e.g, EM pump, doublewall S/G, IHX) will be fabricated by Toshiba and transported to factory where the reactor module is assembled. Metal Fuel Metal Fuel will be fabricated in US for the initial core. 21/28
22 1. 4S Key Features 2. Demonstration of Key Components 3. Economics 4. Licensing 5. Concluding Remarks 22/28
23 Licensing Schedule Pre-application Review Design Approval Design Description Long Life Metallic Fuel Seismic Base Isolation Safety Analysis PIRT I (Design Base Accident) Principle Design Criteria Technical Reporting Plan Emergency Planning Core Design Analysis Submitted Aircraft Hazard Plan I&C PIRT II (Beyond Design Base Accident) Safety design Prevention of Severe Accidents Plant Dynamics Analysis code ANS54.1 WG Toshiba and WEC are participating in the ANS54.1 WG 23/28
24 Development of 4S Principal Design Criteria CRBR SER 10CFR50 App. A ANSI/ANS-54.1 PRISM PSER 4S design concept Evaluate Accept, modify, or add new criteria Passive LWR licensing 4S PDC CRBR: Clinch River Breeder Reactor, FSER: Final Safety Evaluation Report, PRISM: Power Reactor Innovative Small Module, PSER: Preliminary Safety Evaluation Report 24/28
25 Experiences on NRC Pre-review Process No other critical issue in developing 4S PDC based on LWR GDC has been identified except sodium-related matters. GDC for sodium-cooled reactors should be established. Also, no critical issue has been identified in Regulatory Guides applicability except sodium-cooled reactor matters (not specific to 4S). The 4S design conformance to the Policy Statement on Regulation of Advanced Nuclear Power Plants has been confirmed. We are actively participating in ANS 54.1 WG. 25/28
26 1. 4S Key Features 2. Demonstration of Key Components 3. Economics 4. Licensing 5. Concluding Remarks 26/28
27 Concluding Remarks 4S design incorporates feature such as longrefueling interval, passive safety, low maintenance requirements, and high security. 4S has advantages of ease of operation and maintenance, and flexibility. 10 MWe-4S is now in progress of the pre-application review by USNRC. Toshiba is participating in the activity to establish the LMR regulatory framework. The DA application of 4S to USNRC in 2012 is planned. 27/28
28 28/28
Overview of fast reactor development of Toshiba 4S and TRU burner
PSN Number: PSNN-2014-0885 Document Number: AFT-2014-000308 Rev.000(0) Overview of fast reactor development of Toshiba 4S and TRU burner Toshiba Corporation Power Systems Company 2014 Toshiba Corporation
More informationSUPER-SAFE, SMALL AND SIMPLE REACTOR (4S, TOSHIBA DESIGN)
SUPER-SAFE, SMALL AND SIMPLE REACTOR (4S, TOSHIBA DESIGN) Toshiba Corporation and Central Research Institute of Electric Power Industry (CRIEPI), Japan Overview Full name Super-Safe, Small and Simple Reactor
More informationCurrent Status and Future Challenges of Innovative Reactors Development in Japan
Innovation for Cool Earth Forum 2017, Tokyo, Japan, October 4-5, 2017 Current Status and Future Challenges of Innovative Reactors Development in Japan 5 October, 2017 Yutaka Sagayama Assistant to the President
More informationLast Twenty Years Experiences with Fast Reactor in Japan. Kazumoto Ito and Tsutomu Yanagisawa Japan Atomic Energy Agency (JAEA)
Last Twenty Years Experiences with Fast Reactor in Japan Kazumoto Ito and Tsutomu Yanagisawa Japan Atomic Energy Agency (JAEA) 1 Fast Reactor Winter FBR project terminations - The U.S.: Clinch River Breeder
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 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 informationNRC s Advanced Reactor Program. Edward Baker Advanced Reactor Program Office of New Reactors
NRC s Advanced Reactor Program Edward Baker Advanced Reactor Program Office of New Reactors TOPICS Licensing Process Commission Policy Statement on Advanced Reactors Vendors requesting early interaction
More informationGT-MHR OVERVIEW. Presented to IEEE Subcommittee on Qualification
GT-MHR OVERVIEW Presented to IEEE Subcommittee on Qualification Arkal Shenoy, Ph.D Director, Modular Helium Reactors General Atomics, San Diego April 2005 Shenoy@gat.com GT-MHR/LWR COMPARISON Item GT-MHR
More informationREACTOR TECHNOLOGY DEVELOPMENT UNDER THE HTTR PROJECT TAKAKAZU TAKIZUKA
ELSEVIER www.elsevier.com/locate/pnucene Progress in Nuclear Energy; Vol. 47, No. 1-4, pp. 283-291,2005 Available online at www.sciencedirect.com 2005 Elsevier Ltd. All rights reserved s =, E N e E ~)
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 informationNuScale Power Modular and Scalable Reactor. NuScale. Integral Pressurized Water Reactor. Light Water. Light Water.
NuScale Power Modular and Scalable Reactor Overview Full Name NuScale Power Modular and Scalable Reactor Acronym NuScale Reactor type Integral Pressurized Water Reactor Coolant Light Water Moderator Light
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 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 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 informationPreparedness at PFBR Kalpakkam to meet the challenges due to Natural events Prabhat Kumar, Project Director, PFBR, Director construction BHAVINI
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
More informationSmall Modular Reactor Materials R&D Program Materials Coordination Webinar
Small Modular Reactor Materials R&D Program Materials Coordination Webinar William Corwin Office of Advanced Reactor Technologies U.S. Department of Energy August 2012 SMRs Are Strong Contenders to Augment
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 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 informationSmall Modular Reactors (SMRs) What are they? Why are they cool?
Westinghouse Non-Proprietary Class 3 Small Modular Reactors (SMRs) What are they? Why are they cool? Alex Harkness SMR Design Lead/Fellow Engineer ANS Meeting Rocky Hill, CT January 19, 2012 1 Westinghouse
More informationDOE Small Modular Reactor Licensing Technical Support Program Overview for National Conference of State Legislatures June 19, 2014
DOE Small Modular Reactor Licensing Technical Support Program Overview for National Conference of State Legislatures June 19, 2014 Tim Beville Office of Nuclear Energy U.S. Department of Energy Administration
More informationDesign of Traditional and Advanced CANDU Plants. Artur J. Faya Systems Engineering Division November 2003
Design of Traditional and Advanced CANDU Plants Artur J. Faya Systems Engineering Division November 2003 Overview Canadian Plants The CANDU Reactor CANDU 600 and ACR-700 Nuclear Steam Supply Systems Fuel
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 informationAssessment of High Temperature Gas-Cooled Reactor (HTGR) Capital and Operating Costs
Document ID: TEV-96 Revision ID: 0/09/202 Technical Evaluation Study Project No. 23843 Assessment of High Temperature Gas-Cooled Reactor (HTGR) Capital and Operating Costs 0/09/202 TEV-96 0/09/202 Page:
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 informationNuclear Power A Journey of Continuous Improvement
Nuclear Power A Journey of Continuous Improvement Westinghouse Non Proprietary Class 3 Our Place in Nuclear History Innovation 1886 and forever Implementation & Improvement 1957 through Today Renaissance
More informationSafety design approach for JSFR toward the realization of GEN-IV SFR
Safety design approach for JSFR toward the realization of GEN-IV SFR Advanced Fast Reactor Cycle System R&D Center Japan Atomic Energy Agency (JAEA) Shigenobu KUBO Contents 1. Introduction 2. Safety design
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 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 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 informationHTR reactors within Polish strategy of nuclear energy development Cooperation with Japan
HTR reactors within Polish strategy of nuclear energy development Cooperation with Japan Taiju SHIBATA Senior Principal Researcher Group Leader, International Joint Research Group HTGR Hydrogen and Heat
More informationWestinghouse AP1000. Reactor
Westinghouse AP1000 A Third Generation Nuclear Reactor International Council on Systems Engineering (INCOSE) September 18, 2013 Andrew Drake, PMP Director, AP1000 Engineering Completion Engineering, Equipment
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 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 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 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 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 informationDESIGN 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 informationSASOR Canada Ltd. Tetra Tech Inc. 4S reactor applications - Economic case studies. May 2009
SASOR Canada Ltd Tetra Tech Inc. 4S reactor applications - Economic case studies May 2009 Agenda Roles of Tetra Tech and SASOR Canada Why the 4S Reactor and not others Size Production and Cost Environmental
More informationSupplier Opportunities: Traveling Wave Reactor Program
Supplier Opportunities: Traveling Wave Reactor Program The following paragraphs summarize some areas in which TerraPower plans to engage supplier support for development and fabrication of fuel and related
More informationSodium Fast Reactors Systems and components (Part 2)
IAEA Education &Training Seminar on Fast Reactor Science and Technology CNEA Bariloche, Argentina October 1 5, 2012 Sodium Fast Reactors Systems and components (Part 2) Dr. Christian LATGE Nuclear Technology
More informationUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C SAFETY EVALUATION REPORT
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION REPORT Docket No. 72-1040 HI-STORM UMAX Canister Storage System Holtec International, Inc. Certificate of Compliance
More informationSafety Design Requirements and design concepts for SFR
Safety Design Requirements and design concepts for SFR Reflection of lessons learned from the Fukushima Dai-ichi accident Advanced Nuclear System Research & Development Directorate Japan Atomic Energy
More informationNUCLEAR POWER NEW NUCLEAR POWER PLANTS IN 2012
NUCLEAR POWER NEW NUCLEAR POWER PLANTS IN 2012 AP1000 IN FEBRUARY 2012, THE FIRST NUCLEAR POWER PLANTS IN THE US IN 35 YEARS WERE LICENSCED TO BEGIN CONSTRUCTION. TWO WESTINGHOUSE AP1000 NUCEAR REACTOR
More informationSmall Modular Reactor Designs and Technologies for Near-Term Deployments Design Identification and Technology Assessment IAEA
Technology Assessment for New Nuclear Power Programmes Vienna International Centre, M3, 1 3 September 2015 Small Modular Reactor Designs and Technologies for Near-Term Deployments Design Identification
More informationNUCLEAR SMALL MODULAR REACTOR
NUCLEAR SMALL MODULAR REACTOR DESCRIPTION A Small Modular Reactors (SMR) is a nuclear power plant that is smaller in size (300 MW or less) than current generation base load plants (1,000 MW or higher).
More informationSMR INTEGRATION OF NUSCALE SMR WITH DESALINATION TECHNOLOGIES
Proceedings of the ASME 2014 Small Modular Reactors Symposium SMR2014 April 15-17, 2014, Washington, D.C., USA SMR2014-3392 INTEGRATION OF NUSCALE SMR WITH DESALINATION TECHNOLOGIES D. T. Ingersoll NuScale
More informationStatus report Chinese Supercritical Water-Cooled Reactor (CSR1000)
Status report Chinese Supercritical Water-Cooled Reactor (CSR1000) Overview Full name Chinese Supercritical Water-Cooled Reactor Acronym CSR1000 Reactor type Pressurized Water Reactor (PWR) Coolant Supercritical
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 informationThe design features of the HTR-10
Nuclear Engineering and Design 218 (2002) 25 32 www.elsevier.com/locate/nucengdes The design features of the HTR-10 Zongxin Wu *, Dengcai Lin, Daxin Zhong Institute of Nuclear Energy and Technology, Tsinghua
More informationSmall Modular Reactors & waste management issues
Small Modular Reactors & waste management issues 8 th May 2014, Bucharest International Framework For Nuclear Energy Cooperation Infrastructure development working group meeting Dan Mathers Business Leader
More informationResearch Article A Small-Sized HTGR System Design for Multiple Heat Applications for Developing Countries
International Nuclear Energy Volume 21, Article ID 918567, 18 pages http://dx.doi.org/1.1155/21/918567 Research Article A Small-Sized HTGR System Design for Multiple Heat Applications for Developing Countries
More informationNuclear Innovation in Action Small Modular Reactors (SMRs)
Nuclear Innovation in Action Small Modular Reactors (SMRs) David Shropshire Planning and Economic Studies Connecting Roadmaps for Innovative Nuclear Energy to the NDC Timeline (COP23 Side IETA Pavilion)
More informationWhat Nuclear Reactor Companies Need
September 6, 2017 What Nuclear Reactor Companies Need Scott Bailey Vice President, Supply Chain NuScale Nonproprietary Copyright 2017 NuScale Power, LLC Acknowledgement & Disclaimer This material is based
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 informationNuclear Energy and Hydrogen Production The Japanese Situation
Nuclear Energy and Production The Japanese Situation S. SAITO Vice Chairman, Atomic Energy Commission of Japan. Design, Research and Development and Operation Experiences of HTGR in Japan. Introduction
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 informationSFR System Status and Plans
SFR System Status and Plans Dohee Hahn SFR SSC Chair GIF Symposium San Diego November 15-16, 2012 Outline Overview of SFR R&D Key Priority Objectives Project Status Application of GIF Methodologies Challenging
More informationINTEGRAL EFFECT NON-LOCA TEST RESULTS FOR THE INTEGRAL TYPE REACTOR SMPART-P USING THE VISTA FACILITY
HEFAT7 5 th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics 1- July 7, Sun City, South Africa CK INTEGRAL EFFECT NON-LOCA TEST RESULTS FOR THE INTEGRAL TYPE REACTOR SMPART-P
More informationEconomic potential of modular reactor nuclear power plants based on the Chinese HTR-PM project
Available online at www.sciencedirect.com Nuclear Engineering and Design 237 (2007) 2265 2274 Economic potential of modular reactor nuclear power plants based on the Chinese HTR-PM project Zuoyi Zhang,
More informationApplication for Permission to Extend the Operating Period and Application for Approval of Construction Plans of Unit 3 at Mihama Nuclear Power Station
November 26, 2015 The Kansai Electric Power Co., Inc. Application for Permission to Extend the Operating Period and Application for Approval of Construction Plans of Unit 3 at Mihama Nuclear Power Station
More informationConcept and technology status of HTR for industrial nuclear cogeneration
Concept and technology status of HTR for industrial nuclear cogeneration D. Hittner AREVA NP Process heat needs from industry Steam networks In situ heating HTR, GFR 800 C VHTR > 800 C MSR 600 C SFR, LFR,
More informationDESIGN, SAFETY FEATURES & PROGRESS OF HTR-PM. Yujie DONG INET, Tsinghua University, China January 24, 2018
DESIGN, SAFETY FEATURES & PROGRESS OF HTR-PM Yujie DONG INET, Tsinghua University, China January 24, 2018 Meet the Presenter Dr. Dong is a Professor in Nuclear Engineering at the Tsinghua University, Beijing,
More informationEM 2 : A Compact Gas-Cooled Fast Reactor for the 21 st Century. Climate Change and the Role of Nuclear Energy
EM 2 : A Compact Gas-Cooled Fast Reactor for the 21 st Century Presented at the Canon Institute for Global Studies Climate Change Symposium Climate Change and the Role of Nuclear Energy By Dr. Robert W.
More informationDevelopment of a DesignStage PRA for the Xe-100
Development of a DesignStage PRA for the Xe-100 PSA 2017 Pittsburgh, PA, September 24 28, 2017 Alex Huning* Karl Fleming Session: Non-LWR Safety September 27th, 1:30 3:10pm 2017 X Energy, LLC, all rights
More informationDesign and Safety Aspect of Lead and Lead-Bismuth Cooled Long-Life Small Safe Fast Reactors for Various Core Configurations
Journal of NUCLEAR SCIENCE and TECHNOLOGY, 32[9], pp. 834-845 (September 1995). Design and Safety Aspect of Lead and Lead-Bismuth Cooled Long-Life Small Safe Fast Reactors for Various Core Configurations
More informationProgress on Fast Reactor Development in Japan
Presented for Meeting of the Technical Working Group on Fast Reactors (TWG-FR) (45th Annual Meeting) Progress on Fast Reactor Development in Japan June 20-22, 2012 Hiroaki OHIRA, Nariaki UTO Japan Atomic
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 informationASTEC Model Development for the Severe Accident Progression in a Generic AP1000-Like
ASTEC Model Development for the Severe Accident Progression in a Generic AP1000-Like Lucas Albright a,b, Dr. Polina Wilhelm b, Dr. Tatjana Jevremovic a,c a Nuclear Engineering Program b Helmholtz-ZentrumDresden-Rossendorf
More informationHigh Temperature Gas-Cooled Reactors Now More Than Ever!
High Temperature Gas-Cooled Reactors Now More Than Ever! Dr. Finis SOUTHWORTH Chief Technology Officer AREVA Inc. On behalf of the NGNP Industrial Alliance, LLC Washington DC Section ANS Rockville, MD
More informationPreliminary Cost Information for Nuclear Components. Lee Cadwallader Fusion Safety Program ARIES meeting Gaithersburg, MD, July 27-28, 2011
Preliminary Cost Information for Nuclear Components Lee Cadwallader Fusion Safety Program ARIES meeting Gaithersburg, MD, July 27-28, 2011 Nuclear versus Non-nuclear component costs for mechanical parts
More informationDevelopment of FBR Fuel Cycle Technology in Japan
International Conference on Fast Reactors And Related Fuel Cycles: Development of FBR Fuel Cycle Technology in Japan December 8, 2009 H. FUNASAKA, T. KOYAMA, T. NAMEKAWA and T. NAGATA Advanced Nuclear
More informationFast and High Temperature Reactors for Improved Thermal Efficiency and Radioactive Waste Management
What s New in Power Reactor Technologies, Cogeneration and the Fuel Cycle Back End? A Side Event in the 58th General Conference, 24 Sept 2014 Fast and High Temperature Reactors for Improved Thermal Efficiency
More informationOVER VIEW OF ACCIDENT OF FUKUSHIMA DAI-ICHI NPSs AND FUTURE PLANNING TOWARD D&D
OVER VIEW OF ACCIDENT OF FUKUSHIMA DAI-ICHI NPSs AND FUTURE PLANNING TOWARD D&D 16 NOVEMBER, 2011 Hiroshi RINDO JAPAN ATOMIC ENERGY AGENCY Table of Contents 1. What s happened at Fukushima Dai-Ichi NPSs
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 informationCompact, Deployable Reactors for Power and Fuel in Remote Regions
Compact, Deployable Reactors for Power and Fuel in Remote Regions James R. Powell and J. Paul Farrell Radix Corporation, Long Island, New York Presented by Jerry M. Cuttler Dunedin Energy Systems, LLC
More informationGeneral Atomics Prismatic Modular High Temperature Gas Cooled Reactor. Acronym Prismatic HTR. Reactor Type Gas-cooled Reactor.
General Atomics Prismatic Modular High Temperature Gas Cooled Reactor Full name General Atomics Prismatic Modular High Temperature Gas Cooled Reactor Acronym Prismatic HTR Reactor Type Gas-cooled Reactor
More informationInnovative Nuclear Systems as a Solution to Small Scale Nuclear Energy
INPRO Dialogue Forum on Generation IV Nuclear Energy Systems Vienna, Austria, 13 15 April 2016 Innovative Nuclear Systems as a Solution to Small Scale Nuclear Energy Hadid Subki Nuclear Power Technology
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 informationSafety Analysis of Pb-208 Cooled 800 MWt Modified CANDLE Reactors
Journal of Physics: Conference Series PAPER OPEN ACCESS Safety Analysis of Pb-208 Cooled 800 MWt Modified CANDLE Reactors To cite this article: Zaki Su'ud et al 2017 J. Phys.: Conf. Ser. 799 012013 View
More informationDry storage systems and aging management
Dry storage systems and aging management H.Issard, AREVA TN, France IAEA TM 47934 LESSONS LEARNED IN SPENT FUEL MANAGEMENT Vienna, 8-10 July 2014 AREVA TN Summary Dry storage systems and AREVA Experience
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 informationInternational Thorium Energy Conference 2015 (ThEC15) BARC, Mumbai, India, October 12-15, 2015
International Thorium Energy Conference 2015 (ThEC15) BARC, Mumbai, India, October 12-15, 2015 Feasibility and Deployment Strategy of Water Cooled Thorium Breeder Reactors Naoyuki Takaki Department of
More informationU.S. Department of Energy Advanced Reactor Research and Development Program for Fast Reactors
資料 1 U.S. Department of Energy Advanced Reactor Research and Development Program for Fast Reactors John W. Herczeg Deputy Assistant Secretary for Nuclear Technology Research and Development Office of Nuclear
More informationNSSS Design (Ex: PWR) Reactor Coolant System (RCS)
NSSS Design (Ex: PWR) Reactor Coolant System (RCS) Purpose: Remove energy from core Transport energy to S/G to convert to steam of desired pressure (and temperature if superheated) and moisture content
More informationLead cooled Fast SMR s: (S)STAR, ENHS and ELSY
Lead cooled Fast SMR s: (S)STAR, ENHS and ELSY Craig F. Smith LLNL Chair Professor Naval Postgraduate School The 4th Annual Asia Pacific Nuclear Energy Forum on Small and Medium Reactors (SMRs): Benefits
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 informationNEW POWER REACTOR DESIGNS
NUCLEAR ENERGY RENAISSANCE: ADDRESSING THE CHALLENGES OF CLIMATE CHANGE AND SUSTAINABILITY NCSR DEMOKRITOS Athens May 8, 2008 NEW POWER REACTOR DESIGNS Dimitrios Cokinos Brookhaven National Laboratory
More informationCaroline Schlaseman. MPR Associates Inc.
Small Modular Reactors Caroline Schlaseman Facilitator MPR Associates Inc. HI-SMUR 140: A Safe, Secure, Economic Small Modular Reactor Joy Russell Director, Corporate Business Development Holtec International
More informationSmall Scale Nuclear Power: an Option for Alaska? Gwen Holdmann, Director
Small Scale Nuclear Power: an Option for Alaska? Gwen Holdmann, Director Alaska Center for Energy and Power University of Alaska History Overview of of Nuclear Presentation Energy What is nuclear energy?
More informationJoint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety. Trieste,12-23 October 2015
Joint ICTP- Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety Trieste,12-23 October 2015 Safety classification of structures, systems and components
More informationSmall Modular Reactors
Small Modular Reactors Nuclear Institute Joint Nuclear Energy CDT Event, York University, 24 May 2017 Kevin Hesketh Senior Research Fellow Scope To highlight generic design issues from SMRs But not to
More informationPLANT VOGTLE UNITS 3 AND 4
PLANT VOGTLE UNITS 3 AND 4 ZERO GREENHOUSE GASES Nuclear energy facilities release zero greenhouse gases while producing electricity. A single uranium pellet the size of a pencil eraser produces as much
More informationSafety Implication for Gen-IV SFR based on the Lesson Learned from the Fukushima Dai-ichi NPPs Accident. Ryodai NAKAI Japan Atomic Energy Agency
Safety Implication for Gen-IV SFR based on the Lesson Learned from the Fukushima Dai-ichi NPPs Accident Ryodai NAKAI Japan Atomic Energy Agency Contents Introduction Japanese Government Report to the IAEA
More informationCOMPARISON OF FUEL LOADING PATTERN IN HTR-PM
2nd International Topical Meeting on HIGH TEMPERATURE REACTOR TECHNOLOGY Beijing, CHINA, September 22-24, 2004 #Paper C23 COMPARISON OF FUEL LOADING PATTERN IN HTR-PM Fu Li, Xingqing Jing Institute of
More informationAP1000: The PWR Revisited
AP1000: The PWR Revisited IAEA International Conference on Opportunities and Challenges for Water Cooled Reactors in the 21st Century aolo Gaio estinghouse Electric Company tober 27, 2009 1 Background
More informationHTGR Plant Design. Training Course on High Temperature Gas-cooled Reactor Technology October 19-23, Serpong, Indonesia
HTGR Plant Design Training Course on High Temperature Gas-cooled Reactor Technology October 19-23, Serpong, Indonesia Hiroyuki Sato Japan Atomic Energy Agency GTHTR300: JAEA s Commercial HTGR General features
More informationSMR ASME CODES AND SMALL MODULAR REACTORS
Proceedings of the ASME 2014 Small Modular Reactors Symposium SMR2014 April 15-17, 2014, Washington, D.C., USA SMR2014-3345 ASME CODES AND SMALL MODULAR REACTORS Dennis Demoss Sargent & Lundy LLC Chicago,
More informationStatus of Advanced Reactor Development and Deployment. Global Nexus Initiative Workshop
Status of Advanced Reactor Development and Deployment Global Nexus Initiative Workshop Gary T. Mays, Group Leader Advanced Reactor Systems & Safety Reactor and Nuclear Systems Division February 23, 2016
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 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 information