Status of SMR Designs and their associated Fuel Cycle for Immediate-, Near-, and Long-term Deployment
|
|
|
- Darcy Dean
- 6 years ago
- Views:
Transcription
1 Consultants Meeting on SMR Technology for Near Term Deployment, 2 4 May 2011 Status of SMR Designs and their associated Fuel Cycle for Immediate-, Near-, and Long-term Deployment M. Hadid Subki Nuclear Power Technology Development Section Division of Nuclear Power International Atomic Energy Agency
2 SMRs for Immediate Deployment Name Design Organization Country of Origin Electrical Capacity, Mwe Design Status 1 Pressurized Heavy Water Reactor (PHWR-220) NPCIL India Units in Operation 2 2 Pressurized Heavy Water Reactor (PHWR-540) Pressurized Heavy Water Reactor (PHWR-700) 3 KLT-40S OKBM HTR-PM (Reference HTR-10) Central Argentina de Elementos Modulares (CAREM) Prototype Fast Breed Reactor (PFBR-500) Enhanced CANDU 6 (EC-6) NPCIL India Units in Operation NPCIL India Units under Construction Tsinghua University Russian Federation China, Republic of 70 2 Units Under construction 250 CNEA Argentina 27 IGCAR India 500 Atomic Energy of Canada Limited 8 CNP-300 CNNC Detailed Design, 2 Modules under construction Design Certification toward prototype construction in 2012 Under Construction Commissioning in 2012 Canada 700 Detailed Design China, Republic units in Operation as
3 SMRs for Near-term Deployment Name Design Organization Country of Origin Electrical Capacity, MWe Design Status 1 System Integrated Modular Advanced Reactor (SMART) Korea Atomic Energy Research Institute Republic of Korea 100 Detailed design 2 NuScale NuScale Power United States of America 45/module Plan to apply for certification in January mpower Babcock & Wilcox United States of America 125/module Plant to apply for certification later in BREST-300 RDIPE 5 SVBR-75/100 IPPE 6 ABV6M OKBM Russian Federation Russian Federation Russian Federation 300 Conceptual Design Conceptual Design 11 Conceptual Design 7 8 Super-Safe, Small and Simple (4S) Pebble Bed Modular Reactor (PBMR) Toshiba-CRIEPI Japan 10 Detailed Design ESKOM South Africa 100 Conceptual Design
4 SMRs for Long-term Deployment Name Design Organization Country of Origin Electrical Capacity, MWe Design Status 1 Westinghouse SMR Westinghouse United States of America 200 Conceptual Design 2 Holtec Inherently Safe Modular Underground Reactor (HI-SMUR 140) Holtec United States of America 140 Conceptual Design 3 Hyperion Power Module (HPM) Hyperion Power Generation United States of America 25 Conceptual Design 4 Power Reactor Innovative Small Moduler (PRISM) GE Hitachi United States of America 311 Detailed Design 5 Integrated Modular Water Reactor (IMR) Mitsubishi Japan 350 Conceptual Design 6 Flexblue AREVA-DCNS-CEA France Conceptual Design 7 VK-100/300 RIAR Russian Federation 100/300 Conceptual Design
5 SMR for Immediate Deployment PHWR 220 Full name: PHWR 220 Designer: NPCIL - India Reactor type: Pressurized Heavy Water Reactors Coolant/Moderator: D 2 0 Neutron Spectrum: Thermal Neutrons Thermal/Electric capacity: MWt/210.8MWe Fuel Cycle: Closed end fuel cycle; natural uranium in dioxide form as fuel; The spent fuel bundles are reprocessed and the depleted uranium and plutonium are planned to be used in FBRs. A small quantity of reprocessed depleted uranium is also recycled in PHWRs. Salient Features: Twin unit module, with main plant buildings unitized. Design status: 14 units in Operation
6 SMR for Immediate Deployment KLT-40S Designer: OKBM Afrikantov Russian Federation Reactor type: Pressurized Water Reactors Floating Nuclear Cogeration Plant Coolant/Moderator: H 2 0 Neutron Spectrum: Thermal Neutrons Thermal/Electric capacity: 300 MWt/70 MWe (twin modules) Fuel Cycle: Single-Loading of LEU fuel with initial uranium enrichment <20% to enhance proliferation resistance Salient Features: based on long-term experience of operating nuclear icebreakers; intended for district heating and electricity supply in Russia and electricity supply and desalination in developing countries Design status: 2 units under construction
7 SMR for Immediate Deployment HTR-PM Full name: Modular High Temperature Gas Cooled Reactor Pebble Bed Module Designer: Tsinghua University, Republic of China Fuel: TRISO (UO 2 ) with 8.9% enrichment of fresh fuel element Thermal/Electric capacity: 450 MWt/110 MWe Fuel Cycle: Design burn-up to reach 100GWd/t to reduce fuel cycle cost Salient Features: high operation temperature; multiple-module reactors coupled to one high pressure superheated steam turbine generator, sharing common auxiliary systems Design status: 2 modules under construction
8 SMR for Immediate Deployment CAREM-25 Full name: Central Argentina de Elementos Modulares Designer: The National Atomic Energy Commission of Argentina (CNEA) Reactor type: Integral PWR Coolant/Moderator : Light Water Neutron Spectrum: Thermal Neutrons Thermal/Electrical Capacity: 87.0 MWt/27 MWe Fuel Cycle: 14 months Salient Features: primary coolant system within the RPV, self-pressurized and relying entirely on natural convection. Design status: Design Certification to prepare for prototype deployment by 2012
9 SMR for Immediate Deployment PFBR 500 Full name: Prototype Fast Breed reactor 500 MWe Designer: IGCAR, India Reactor type: Fast Breeder reactor Coolant: Liquid sodium Neutron Spectrum: Fast Neutrons Thermal/Electrical Capacity: 1250 MWt/500 MWe Fuel Cycle: 6 months Salient Features: Passive decay heat removal system; it does not require water for emergency cooling in the case of an accident Design status: 1 unit under construction in Kalpakkam - India; commissioning in 2012
10 SMR for Near-term Deployment SMART Full name: System-Integrated Modular Advanced Reactor Designer: Korea Atomic Energy Research Institute (KAERI), Republic of Korea Reactor type: Integral PWR Coolant/Moderator: Light Water Neutron Spectrum: Thermal Neutrons Thermal/Electrical Capacity: 330 MWt/100 MWe Fuel Cycle: 36-months Salient Features: Passive decay heat removal system in the secondary side; horizontally mounted RCPs; intended for sea water desalination and electricity supply in newcomer countries with small grid Design status: Detailed Design
11 SMR for Near-term Deployment NuScale Full name: NuScale Designer: NuScale Power, USA Reactor type: Integral Pressurized Water Reactor Coolant/Moderator: Light Water Neutron Spectrum: Thermal Neutrons Thermal/Electrical Capacity: 150 MWt/45 MWe Fuel Cycle: on-line refueling Salient Features: Natural circulation cooled; Decay heat removal using containment; built below ground Design status: Plan to apply for certification in January 2012
12 SMR for Near-term Deployment 4: mpower Full name: mpower Designer: Babcock & Wilcox Modular Nuclear Energy, LLC(B&W), United States of America Reactor type: Integral Pressurized Water Reactor Coolant/Moderator: Light Water Neutron Spectrum: Thermal Neutrons Thermal/Electrical Capacity: 500 MWt/125 MWe Fuel Cycle: 48-month or more Salient Features: integral NSSS, CRDM inside reactor vessel; Passive safety that does not require emergency diesel generator Design status: Began pre-application interactions in July Design certification application later in 2012.
13 SMR for Near-term Deployment BREST-OD-300 Designer: RDIPE, Russian Federation Reactor type: Small Liquid Metal (Lead) Fast Reactor Coolant: Lead Fuel: uranium-plutonium mono-nitride Neutron Spectrum: Fast Neutrons Thermal/Electrical Capacity: 700 MWt/300 MWe Fuel Cycle: closed fuel cycle which includes transmutation and in-pile burning of actinides, transmutation of long-lived fission products, radwaste purification from actinides, cooling and final radwaste disposal; Salient Features: Using a two-circuit heat transport system to deliver heat to a supercritical steam turbine. Design status: Conceptual design
14 SMR for Near-term Deployment 4S Full name: Super-Safe, Small and Simple Designer: Toshiba Corporation, Japan Reactor type: Liquid Sodium cooled, Fast Reactor but not a breeder reactor Neutron Spectrum: Fast Neutrons Thermal/Electrical Capacity: 30 MWt/10 MWe Fuel Cycle: without on-site refueling with core lifetime ~30 years. The movable reflector surrounding the core gradually moves, compensating the burn-up reactivity loss over 30 years. Salient Features: power can be controlled by the water/steam system without affecting the core operation Design status: Conceptual Design
15 SMR for Long-term Deployment PRISM Full name: Power Reactor Innovative Small Module Designer: GE Hitachi Nuclear, USA Reactor type: Small Liquid Metal (Sodium) cooled, underground Fast Breeder Reactor Coolant: Sodium Neutron Spectrum: Fast Neutrons Thermal/Electrical Capacity: 840 MWt/311 MWe Fuel Cycle: closed fuel cycle Salient Features: Underground containment on seismic isolators with a passive air cooling ultimate heat sink. Modular design with two reactor modules per power unit (turbine generator). Design status: Conceptual Design
16 SMR for Long-term Deployment Flexblue Full name: Flexblue Designer: DCNS, France Reactor type: Small Liquid Metal (Sodium) cooled, underground Fast Reactor Neutron Spectrum: Thermal Electrical Capacity: MWe Fuel Cycle: --- Salient Features: based on the experience of building nuclear submarine and aircraft carrier; the nuclear capsule lowered m to the seabed, at a site 5-15 km from the coast; electricity supplied to coast by submarine power cables Design status: Conceptual Design
17 SMR for Long-term Deployment Westinghouse SMR Full name: Westinghouse SMR Designer: Westinghouse Electric Company, USA Reactor type: Integral Pressurized Water Reactor Coolant/Moderator: Light Water Neutron Spectrum: Thermal Neutrons Thermal/Electrical Capacity: ~620MWt/200 MWe Fuel Cycle: 24 months Salient Features: CRDM inside RPV, horizontally mounted RCPs; referred to AP1000 as the reference plant, instead of to IRIS features Design status: Conceptual Design
18 SMR for Long-term Deployment FBNR Full name: Fixed Bed Nuclear Reactor Designer: Federal University of Rio Grande do Sul, Brazil Reactor type: Integral Pressurized Water & High Temperature Gas cooled Reactor Coolant/Moderator: Light Water Neutron Spectrum: Thermal Neutrons Thermal/Electrical Capacity: 134 MWt/40 MWe Fuel Cycle: Flexible fuel cycle Salient Features: conceptual PWR with CERMET spherical fuel; the core becomes empty of fuel elements, and nuclear criticality ceases, should any undesired situation occur. Design status: Conceptual Design
19 SMR for Long-term Deployment Hyperion Full name: Hyperion Power Module Designer: Hyperion Power Generation, Inc., USA Reactor type: Lead-bismuth eutectic, primary and secondary loops Coolant: Lead-bismuth Neutron Spectrum: Fast Neutrons Thermal/Electrical Capacity: 70 MWt/25 MWe Fuel Cycle: 10 years Salient Features: underground NPP Design status: Conceptual design
Development Status of Small and Modular Reactors
Presented at the 24 th Meeting of the TWG - NPPIC, on 23 May 2013 at s Press Room Development Status of Small and Modular Reactors M. Hadid Subki Technical Lead for SMR Technology Development Nuclear Power
Global Development and Deployment Plan of Small-Medium Reactors (SMRs)
5 th GIF INPRO Interface Meeting, Vienna, 3 4 March 2011 Global Development and Deployment Plan of Small-Medium Reactors (SMRs) Dr. M. Hadid Subki Technical Lead, SMR Technology Nuclear Power Technology
Global Trends, Prospects and Challenges for Innovative SMRs Deployment
Global Trends, Prospects and Challenges for Innovative SMRs Deployment Thomas Koshy, Head Nuclear Power Technology Development, Division of Nuclear Power, Department of Nuclear Energy Presented to NUCLEAR
Small 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
Small 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
Small 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
NUCLEAR 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).
Innovative 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
STATUS OF SMALL AND MEDIUM SIZED REACTOR DESIGNS
STATUS OF SMALL AND MEDIUM SIZED REACTOR DESIGNS A Supplement to the IAEA Advanced Reactors Information System (ARIS) http://aris.iaea.org @ September 2012 STATUS OF SMALL AND MEDIUM SIZED REACTOR DESIGNS
Prospects and Challenges of Small Modular Reactor Deployments as Option to Enhance Energy Supply Security. IAEA International Atomic Energy Agency
APEC SELF-FUNDED WORKSHOP ON NUCLEAR POWER Sustainable Energy & Technology Asia 2016 (SETA 2016) 25 March 2016, Bangkok International Trade and Exhibition Centre Bangkok, THAILAND Prospects and Challenges
Chemical Engineering 693R
Chemical Engineering 693R Nuclear Reactor Design and Analysis Lecture 2 Reactors and Core Concepts Spiritual Thought 2 Historically, fear has often been used as a means to get people to take action. Parents
Advances in Small Modular Reactor Design and Technology Development for Near-term Deployment
ESI-CIL Nuclear Governance Project Conference Series Small Modular Nuclear Reactors: The Outlook for Deployment Jen Tanglin Hotel, Singapore, 8 th November 2017 Advances in Small Modular Reactor Design
Small 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
ATOMS FOR PEACE THE NEXT GENERATION. Dr. John E. Kelly U.S. Department of Energy, Office of Nuclear Energy September 29, 2016
ATOMS FOR PEACE THE NEXT GENERATION Dr. John E. Kelly U.S. Department of Energy, Office of Nuclear Energy September 29, 2016 MEET THE PRESENTER Dr. John E. Kelly is the Deputy Assistant Secretary for Nuclear
Technology and Financing
Technology and Financing Atam Rao Head Nuclear Power Technology Development Section Department of Nuclear Energy IAEA Technology and financing Technology impacts Cost and Schedule Which impact financing
Potential of Small Modular Reactors
Potential of Small Modular Reactors Energiforsk 2017 January 2017 Dr Fiona Rayment Director Fuel Cycle Solutions UK Experience of Different Reactor Systems Sodium-cooled fast reactors Gas-cooled reactors
Small 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
The Current Status and Perspectives for the Use of Small Modular Reactors for Electricity Generation
The Current Status and Perspectives for the Use of Small Modular Reactors for Electricity Generation 2015 The document describes briefly the current situation and perspectives for the use of Small Modular
Fast 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
SMALL MODULAR REACTORS
SMALL MODULAR REACTORS James T. (Tom) Voss, NRRPT, CHP Los Alamos National Laboratory Health Physics Measurements Group (RP-SVS) Operated by Los Alamos National Security, LLC for the U.S. Department of
Advances in Small Modular Reactor Technology Developments. A Supplement to: IAEA Advanced Reactors Information System (ARIS) 2016 Edition
Advances in Small Modular Reactor Technology Developments A Supplement to: IAEA Advanced Reactors Information System (ARIS) 2016 Edition ADVANCES IN SMALL MODULAR REACTOR TECHNOLOGY DEVELOPMENTS 2016 Edition
SAFETY, SITTING, EMERGENCY PLANNING ISUES FOR SMR DEPLOYMENT IN INDONESIA
SAFETY, SITTING, EMERGENCY PLANNING ISUES FOR SMR DEPLOYMENT IN INDONESIA PANDE Made Udiyani National Nuclear Energy Agency (BATAN) Republic of Indonesia INPRO Dialogue Forum on Legal and Institutional
Advanced Reactors Mission, History and Perspectives
wwwinlgov Advanced Reactors Mission, History and Perspectives Phillip Finck, PhD Idaho National Laboratory Senior Scientific Advisor June 17, 2016 A Brief History 1942 CP1 First Controlled Chain Reaction
Small Modular Reactors. Kristiina Söderholm, PhD Head of Nuclear Technology & Innovation Fortum, Finland
Small Modular Reactors Kristiina Söderholm, PhD Head of Nuclear Technology & Innovation Fortum, Finland 2016 Content What are SMRs? What are challenges for SMRs? Why do SMRs play a role in the future?
Nuclear Power One Year After Fukushima
Nuclear Power One Year After Fukushima Where is it Heading? Alexander Glaser CMI Annual Conference Princeton University, April 17, 2012 Revision 8x 5 6 4 3 2 1 Fukushima-Daiichi Plant Source: TEPCO, undated
Small Reactors. Cindy Klotz Facilitator Black & Veatch
Small Reactors Cindy Klotz Facilitator Black & Veatch Small Modular Reactors Mark Gake, P.E. Nuclear Chief Engineer, Black & Veatch July 23, 2013 Agenda What is an SMR? SMR Advantages SMR Designs in Development
Development of nuclear energy and position on small reactors in the Czech Republic
Development of nuclear energy and position on small reactors in the Czech Republic Jozef Mišák, Director for Strategy Nuclear Research Institute Rez plc International Conference on Prospects of Small Nuclear
Small Nuclear Power Reactors
1 of 10 11/21/2005 5:01 PM Small Nuclear Power Reactors UIC Nuclear Issues Briefing Paper # 60 November 2005 There is revival of interest in small and simpler units for generating electricity from nuclear
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
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
Design 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
Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies May 2008
1944-16 Joint Reaction Data for Advanced Reactor Technologies 19-30 May 2008 Advanced Small and Medium Sized Reactors (SMRs) - Part 2 V. Kuznetsov IAEA Vienna Austria Advanced Small and Medium Sized Reactors
Nuclear 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
Small Modular Reactors A Window on Nuclear Energy
Small Modular Reactors A Window on Nuclear Energy An Energy Technology Distillate from the Andlinger Center for Energy and the Environment at Princeton University Contributors Alexander Glaser, M.V. Ramana,
The Future of Small and Medium Sized Nuclear Reactors
The Future of Small and Medium Sized Nuclear Reactors 2009 and Beyond Presentation Outline Distinguish from Large Commercial Reactors History Application Current Presence in the United States and Internationally
Latest Developments in Small Modular Reactors. Dr Adi Paterson Annual Meeting of Four Societies 2015
Latest Developments in Small Modular Reactors Dr Adi Paterson Annual Meeting of Four Societies 2015 Argonne National Laboratory (West) Idaho, USA EBR-1 First Nuclear Electricity - December 20 1951 Breaking
Status 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
Evaluation of a Business Case for Safeguards by Design in Nuclear Power Reactors
PNNL-22102 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 Evaluation of a Business Case for Safeguards by Design in Nuclear Power Reactors TW Wood VA Lewis MD Zentner AM Seward
Next and Last Generation of Nuclear Power Plants Paul Howarth
Next and Last Generation of Nuclear Power Plants Paul Howarth Exec Director, Dalton Nuclear Institute IMechE Branch Meeting Jan 2009 Order of Service Introduction to status of advanced systems The 3 contending
Module 12 Generation IV Nuclear Power Plants. Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria
Module 12 Generation IV Nuclear Power Plants Prof.Dr. H. Böck Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria boeck@ati.ac.at Generation IV Participants Evolution of Nuclear
NRC 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
Small 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?
AFTER A REVIEW of designs of nine
Operations REPORT Study outlines reactor designs that may be ready for deployment by decade s end A Department of Energy report examines the feasibility of deploying small, modular, nuclear reactors in
Concept 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,
NEW 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
DOE 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
IAEA Technical Meeting on Passive Shutdown Systems for LMFR Vienna, October Overview of IAEA Activities in the Field of Safety of FR
Technical Meeting on Passive Shutdown Systems for LMFR Vienna, 20-22 October 2015 Overview of Activities in the Field of Safety of FR Outline of the Technical Meeting Stefano Monti Nuclear Power Technology
FOURTH GENERATION REACTOR CONCEPTS
Chapter 6 FOURTH GENERATION REACTOR CONCEPTS M. Ragheb 3/11/2014 6.1 INTRODUCTION Nuclear power plants across the globe are producing about 16 percent of the world s electricity. With the depletion of
Specific Design Consideration of ACP100 for Application in the Middle East and North Africa Region
Specific Design Consideration of ACP100 for Application in the Middle East and North Africa Region IAEA Technical Meeting on Technology Assessment of Small Modular Reactors for Near Term Deployment 2 5
Plutonium Production in Small, Fast Reactors (SMRs)
www.toshiba.co.jp Plutonium Production in Small, Fast Reactors (SMRs) Friederike Frieß IANUS, TU Darmstadt 20.03.2014 Overview Definition of SMR Proliferation risks and SMRs Sodium-cooled reactor model
Nuclear Energy. Weston M. Stacey Callaway Regents Professor Nuclear and Radiological Engineering Program Georgia Institute of Technology
Nuclear Energy Weston M. Stacey Callaway Regents Professor Nuclear and Radiological Engineering Program Georgia Institute of Technology NAE Symposium The Role of Alternative Energy Sources in a Comprehensive
Nuclear 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)
Nuclear Power Reactors. Kaleem Ahmad
Nuclear Power Reactors Kaleem Ahmad Outline Significance of Nuclear Energy Nuclear Fission Nuclear Fuel Cycle Nuclear Power Reactors Conclusions Kaleem Ahmad, Sustainable Energy Technologies Center Key
Technology 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
Nuclear Cogeneration
Nuclear Cogeneration International Workshop on Acceleration and Applications of Heavy Ions 26 February - 10 March 2012 Heavy Ion Laboratory, Warsaw, Poland Ludwik Pieńkowski Heavy Ion Laboratory University
Characteristics of Modular Fast Reactor SVBR-100 Using Thorium-Uranium (233) Fuel
Characteristics of Modular Fast Reactor SVBR-100 Using Thorium-Uranium (233) Fuel G.I. Toshinsky ab, O.G. Komlev b, I.V. Tormyshev b, N.N. Novikova b, K.G. Mel nikov b a -JSC AKME-Engineering, Moscow,
BN-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.
Advanced 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
INAC-ENFIR Recife, November Molten Salt Nuclear Reactors
INAC-ENFIR Recife, November 24-29 2013 Molten Salt Nuclear Reactors Dr Cassiano R E de Oliveira Department of Chemical and Nuclear Engineering The University of New Mexico cassiano@unm.edu Outline Motivation
Generation 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
ENCAPSULATED NUCLEAR HEAT SOURCE REACTORS FOR ENERGY SECURITY
15 th Pacific Basin Nuclear Conference, Sidney, Australia, October 15-20, 2006 ENCAPSULATED NUCLEAR HEAT SOURCE REACTORS FOR ENERGY SECURITY Greenspan E 1., Hong S.G. 1,2, Monti L 1,3., Okawa T 1,4., Sumini
Design Features, Economics and Licensing of the 4S Reactor
PSN Number: PSN-2010-0577 Document Number: AFT-2010-000133 rev.000(2) Design Features, Economics and Licensing of the 4S Reactor ANS Annual Meeting June 13 17, 2010 San Diego, California Toshiba Corporation:
Westinghouse 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.
Nuclear 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
Nuclear energy in Europe
Nuclear energy in Europe Contribution to the Future Low Carbon Energy Society Dr. Ákos Horváth Director General, MTA Centre for Energy Research (HU) akos.horvath@energia.mta.hu EASAC/JRC meeting on Nuclear
Small and Modular Reactor Development, Safety and Licensing in Korea
Small and Modular Reactor Development, Safety and Licensing in Korea IAEA TWG-LWR Vienna, June 18-20, 2013 Presented by Jong-Tae Seo 1 Outline I. SMR Development in Korea II. SMART Development III. SMART
RAHP News Letter. No.16. High Temperature Gas Cooled Reactor (HTGR) Developments in the World. ~Present Status and Future Plans~ March 2017
RAHP News Letter No.16 High Temperature Gas Cooled Reactor (HTGR) Developments in the World ~Present Status and Future Plans~ March 2017 Research Association of High Temperature Gas Cooled Reactor Plant
Small 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
Nuclear-Power Ammonia Production
Nuclear-Power Ammonia Production William L. Kubic, Jr. Process Engineering, Modeling,and Analysis Group, New Mexico October 9, 2006 Why Nuclear-Powered Ammonia Production? Many in the nuclear community
Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies May Small and Medium Sized Reactors
2141-1 Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies 3-14 May 2010 Small and Medium Sized Reactors Stanculescu A. IAEA Vienna AUSTRIA Advanced Small and Medium Sized
Neighborhood Nukes: Great for America? Great for the Environment? Great for Al Qaeda?
Neighborhood Nukes: Great for America? Great for the Environment? Great for Al Qaeda? Stephanie N. Lubiak June 2011 Advisor: Alain L. Kornhauser Submitted in partial fulfillment of the requirements for
INNOVATIVE NUCLEAR REACTOR DEVELOPMENT. Opportunities for International Co-operation
INNOVATIVE NUCLEAR REACTOR DEVELOPMENT Opportunities for International Co-operation INTERNATIONAL ENERGY AGENCY 9, rue de la Fédération, 75739 Paris, cedex 15, France The International Energy Agency (IEA)
U.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
Nuclear 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
Economic 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,
IAEA-TECDOC-1622 Status and Trends of Nuclear Technologies
IAEA-TECDOC-1622 Status and Trends of Nuclear Technologies Report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) IAEA-TECDOC-1622 Status and Trends of Nuclear Technologies
DESIGN, 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,
Global Perspectives on SMRs Developing Countries Expectations
Global Perspectives on SMRs Developing Countries Expectations Dr Atam Rao Head Nuclear Power Technology Development Jun 18, 2010 The 4 th Annual Asia-Pacific Nuclear Energy Forum on Small and Medium Reactors
Nuclear Energy for Remote Applications
Nuclear Energy for Remote Applications 23 October, 2014 Michael Kuca (University of Alaska) Vishal Patel (Texas A&M) Alana Vilagi (University of Alaska) 1 Objectives Consider GenIII+/GenIV nuclear power
Module 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
Small Modular Reactors The Real Nuclear Renaissance?
Small Modular Reactors The Real Nuclear Renaissance? Institute of Physics, Nuclear Industry Group Birchwood, 25 May 2016 Juan Matthews FInstP Dalton Nuclear Institute and School of Materials The University
RAHP News Letter. HTGR Developments in the World ~Present Status and Future Plans~ March 2013
RAHP News Letter No.12 HTGR Developments in the World ~Present Status and Future Plans~ March 2013 Research Association of High Temperature Gas Cooled Reactor Plant (RAHP), Tokyo, Japan Introduction: This
THE JAMES A. BAKER III INSTITUTE FOR PUBLIC POLICY NEW ENERGY TECHNOLOGIES:
THE JAMES A. BAKER III INSTITUTE FOR PUBLIC POLICY OF RICE UNIVERSITY NEW ENERGY TECHNOLOGIES: A POLICY FRAMEWORK FOR MICRO-NUCLEAR TECHNOLOGY SMALL INNOVATIVE REACTOR DESIGNS USEFUL ATTRIBUTES AND STATUS
Seminar on Coolants for Fast Neutron Reactors. Frank Carré & Yves Bamberger CEA, Nuclear Energy Division, France
Seminar on Coolants for Fast Neutron Reactors Frank Carré & Yves Bamberger CEA, Nuclear Energy Division, France Maturity of Fast Reactor Types Sodium fast reactor ~400 reactor.year of operating experience
High Temperature Reactors in the Nuclear Energy System from position of the Hydrogen Economy
High Temperature Reactors in the Nuclear Energy System from position of the Hydrogen Economy P.N. Alekseev, A.L. Balanin, P.A. Fomichenko, E.I. Grishanin, D.A. Krylov, V.A. Nevinitsa, T.D. Schepetina,
PLUTONIUM 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
AUTONOMOUS BATTERY REACTORS
AUTONOMOUS BATTERY REACTORS M. Ragheb 3/25/2017 INTRODUCTION Nuclear energy provides 20 percent of the electricity produced in the USA and 16 percent throughout the world. Significant capital investment
Technology Development Status Report Small Modular Reactors
The 10th GIF- Interface Meeting Vienna, Austria, 11 12 April 2016 Technology Development Status Report Small Modular Reactors Hadid Subki Nuclear Power Technology Development Section, Division of Nuclear
Evolution 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)
A Compact Transportable Nuclear Power Reactor
A Compact Transportable Nuclear Power Reactor Can be rapidly deployed to remote locations to support oil recovery, disaster relief and basic infrastructure Paul Farrell and James Powell 1 Brookhaven Technology
CAREM: 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
Non-Electric Applications of Nuclear Energy
Non-Electric Applications of Nuclear Energy I. Khamis Nuclear Power Technology Development Section Department of Nuclear Energy Contents Introduction An overview of current experience on nonelectric applications
Radiochemistry Webinars
National Analytical Management Program (NAMP) U.S. Department of Energy Carlsbad Field Office Radiochemistry Webinars Nuclear Fuel Cycle Series Introduction to the Nuclear Fuel Cycle In Cooperation with
JAEA s Efforts for Reduction of Radioactive Wastes
International Symposium on Present Status and Future Perspective for Reducing of Radioactive Wastes JAEA s Efforts for Reduction of Radioactive Wastes February 17, 2016 Yasushi Taguchi Executive Vice President
IAEA-TECDOC-1444 Optimization of the coupling of nuclear reactors and desalination systems
IAEA-TECDOC-1444 Optimization of the coupling of nuclear reactors and desalination systems Final report of a coordinated research project 1999 2003 June 2005 IAEA-TECDOC-1444 Optimization of the coupling
GT-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
Design 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
Generation IV Reactors
Generation IV Reactors Richard Stainsby National Nuclear Laboratory Recent Ex-Chair of the GFR System Steering Committee Euratom member of the SFR System Steering Committee What are Generation IV reactors?
Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies May 2008
1944-15 Joint Reaction Data for Advanced Reactor Technologies 19-30 May 2008 Advanced Small and Medium Sized Reactor (SMRs) Part 1 V. Kuznetsov IAEA Vienna Austria Advanced Small and Medium Sized Reactors
Desalination. A. Introduction
Desalination A. Introduction 1. Seventy percent of the planet is covered with water, but only 2.5% of that is freshwater. Nearly 70% of this freshwater is frozen in the icecaps of Antarctica and Greenland.
CONTENTS. ACRONYMS... v. 1. AN ESSENTIAL ROLE FOR NUCLEAR ENERGY Meeting the Challenges of Nuclear Energy s Essential Role...
1 2 iii CONTENTS ACRONYMS... v 1. AN ESSENTIAL ROLE FOR NUCLEAR ENERGY... 1 1.1 Meeting the Challenges of Nuclear Energy s Essential Role... 1 2. FINDINGS OF THE ROADMAP... 3 2.1 Generation IV Nuclear