Generation IV Reactor Systems and Renewable Energy

Total Page:16

File Type:pdf, Size:1020Kb

Generation IV Reactor Systems and Renewable Energy Generation IV reactor systems and Renewable Energy Hideki Kamide Chair-Elect, Policy Group The Generation IV International Forum (GIF) NICE Future Webinar, December 2018 Contents I. The Generation IV International Forum II. Relation between Nuclear and Renewable III. What can be done by Gen-IV Reactor Systems? IV. Challenges for the industrial deployment of GEN-IV reactors NICE Future Webinar, December 2018 2 I. The Generation IV International Forum 3 Generation of Nuclear Energy Systems Current nuclear plants in operation are mainly Gen-II and Gen-III reactors. Evolutionary LWR, Small modular reactors, and Gen-IV reactors are expected as next generation nuclear power plants. Gen-IV reactors are expected to enter commercial phase after 2030 NICE Future Webinar, December 2018 4 History of Generation IV International Forum (GIF) USA proposed a bold initiative in 2000 The vision was to leapfrog LWR technology and collaborate with international partners to share R&D on advanced nuclear systems. GIF Charter was signed in Jul. 2001, and extended in 2011. Gen IV concept defined via technology goals and legal framework Technology Roadmap released in 2002, and updated in Jan. 2014. 2 year study with more than100 experts worldwide Nearly 100 reactor designs evaluated and down selected to 6 most promising concepts: SFR, VHTR, LFR, SCWR, GFR and MSR. Framework Agreement (FA) was signed in Feb. 2005, and extended in 2015 for another 10 years. France, Japan, Korea, USA are signed in Feb. 2015 and Russia, Switzerland, and South Africa signed in after Feb. in 2015 respectively, Canada and EU signed in 2016. Australia joined in 2017 and UK deposited its instrument of accession in 2018 as new member countries. Signing ceremony of FA NICE Future Webinar, December 2018 5 Generation IV Goals Sustainability Long term fuel supply Minimize waste and long term stewardship burden Safety & Reliability Very low likelihood and degree of core damage Eliminate need for offsite emergency response Economics Life cycle cost advantage over other energy sources Financial risk comparable to other energy projects Proliferation Resistance & Physical Protection Unattractive materials diversion pathway Enhanced physical protection against terrorism NICE Future Webinar, December 2018 6 Six Generation IV Reactors Pool type Loop Very High Temperature Gas-cooled Fast Reactor type Reactor (VHTR) (GFR) Sodium-cooled Fast Reactor (SFR) A fluoride salt coolant high- temperature reactor (FHR) Molten salt serves as the coolant of solid fuel core Molten fuel salt type Supercritical Water Lead-cooled Fast Reactor cooled Reactor (SCWR) (LFR) Molten Salt Reactor (MSR) NICE Future Webinar, December 2018 7 Comparison of Gen-IV Reactors Neutron Outlet temp. Power System Coolant Fuel cycle Spectrum ( ) (MWe) Sodium-cooled ℃ Fast Reactor Fast Sodium 500-550 Closed 50-1500 (SFR) Very High Temperature Thermal Helium 900-1000 Open 250-300 Reactor (VHTR) Gas-cooled Fast Fast Helium 850 Closed 1200 Reactor (GFR) Supercritical Thermal/ Open/ Water-cooled Fast Water 510-625 Closed 300-1500 Reactor (SCWR) Lead-cooled Fast Fast Lead 480-570 Closed 20-1200 Reactor (LFR) Molten Salt Thermal/ Fluoride/ Reactor (MSR) Fast Chloride 700-800 Closed 1000 salts NICE Future Webinar, December 2018 8 Fourteen Current Members of GIF Argentina* Japan Australia Republic of Korea Brazil* Russian Federation Canada Republic of South Africa People’s Republic of China Switzerland Euratom United Kingdom France United States *Non-active member NICE Future Webinar, December 2018 9 II. Relation between Nuclear and Renewable 10 Current status of Fukushima Daiichi Nuclear Power Station (NPS) 30-40 years for decommissioning 43,000 of people are still evacuated. NICE Future Webinar, Decemberhttp://www.meti.go.jp/english/earthquake/nuclear/decommissioning/index.html 2018 http://www.meti.go.jp/english/earthquake/nuclear/decommissioning/pdf/20180827_roadmap.pdf 11 Needs for CO2-free Energy: Global warming & Decarbonized society 35 Toward Zero in 2100 30 Paris Agreement (COP21) 25 -0.4Gt every year 20 15 More than 66 Gt of CO2 emissions have been CO2 [ Gt] avoided through the use of nuclear energy since 1971. 10 Nuclear electricity today avoids global emissions of about 1.7 Gt CO every year, accounting for 40% of low 5 2 carbon electricity generation worldwide. 0 2000 2003 2006 2009 2012 2015 2018 2021 2024 2027 2030 2033 2036 2039 2042 2045 2048 Years CO2 data: Global Energy & CO2 Status Report 2017, IEA NICE Future Webinar, December 2018 12 Earthquake in Hokkaido and Blackout in 2018 An Earthquake in this summer Hokkaido resulted in Blackout of electricity in the entire area of Hokkaido for several days long. Japan Large thermal power reactor, which covers half of Hokkaido, was shutdown by the Earthquake. Total of 2.95 million households* lost the electricity. Such large-scale blackout is the first time in Japan. Reliability of The land-area of Hokkaido is the Grid is high-lighted. similar to Ireland! Widespread blackouts occurred all over the world North America(1989,2003), South America(2009), Moscow(2005) Europe(2003,2005), Asia(2011,2017) Stable and Reliable Grid is a significant issue of electricity supply. *Source: Reuter News: September 7, 2017 https://www.reuters.com/article/us-japan-quake-power/power-returning-to-hokkaido-but-quake-exposes-flaws-of-japan-grid-idUSKCN1LN1EM 13 Goals for Generation IV Reactor systems in GIF Four pillars Safety & Proliferation Sustainability Economics Resistance & Reliability Physical Protection Clean air and Very low likelihood of Life cycle cost Unattractive effective use of U Core Damage Financial risks diversion Minimize waste No need of Offsite Physical and burden emergency response protection Examples of Emerging influence factors Stakeholders, Low carbon society, Drivers from market Hybrid systems Society Private sectors National status, Commercialize Grid reliability Historical circumstance pathway National policy NICE Future Webinar, December 2018 14 Pathways to commercialize Six reactor systems to achieve GIF goals SFR LFR MSR GFR SCWR VHTR Common attributions and Challenges Reliable and Sustainable power supply in Decarbonized Society (Combination with other CO2 free energy systems) Safety enhancement depended on reactor types Cost competitive with these attributions Enhancement of R&D Collaborations on these issues NICE Future Webinar, December 2018 15 World 2˚C energy policy scenario by IEA IEA, WORLD ENERGY OUTLOOK-2017,P244 Intermittent renewables emerging rapidly in the world, but even so dispatchable zero CO2 energies are 20%, Intermittents are 30% NICE Future Webinar, December 2018 16 Example of daily intermittent patterns (Germany) 9AM Production 3PM Consumption Getting Wind and Sun onto the Grid, p.35-36 OECD/IEA(2017) NICE Future Webinar, December 2018 17 CO2 emission depended on power supply systems: 2015 Sweden France Washington Denmark California Germany Japan gCO2/kWh gCO2/kWh 106 174 282 450 540 11 46 gCO2/kWh gCO2/kWh gCO2/kWh gCO2/kWh gCO2/kWh Stable 88% 88% 76% 15% 26% 25% 12% Renewables 53% 11% 69% 15% 16% 11% 11% Nuclear 35% 78% 7% 0% 9% 14% 1% Intermi- ttent 10% 5% 6% 51% 14% 18% 4% Solar 0% 1% 0% 2% 8% 6% 3% Wind 10% 4% 6% 49% 6% 12% 1% Fossil energy 2% 7% 17% 34% 60% 56% 85% IEACO2 emissions from fuel combustion 2017 NICE Future Webinar, December 2018 18 III. What can be done by Gen-IV Reactor Systems? 19 Multiple pathways to Commercialization SFR LFR MSR GFR SCWR VHTR Example of contributions / attributions Sustainability Hybrid systems Cost Competitive Reliable grid: Load following, Heat storage R&Ds on Innovative systems Heat usage for hydrogen, Water desalination. GEN-3 + feedback experience Effective Use of Uranium Resources Minimize radioactive waste and burden Safety Passive features of Reactivity feedbacks, Passive shutdown systems, Passive decay heat removals, Natural circulations, etc. Safety Design Criteria for International Safety Standards NICE Future Webinar, December 2018 20 Example of Hybrid system –integration with RES- + Constant Power supply Nuclear Power output adjustment 再生可能エネルギー発電所RES Power supply Control Signals 出力 電気出力の制御Power Nuclear (インベントリ)control 電力合成 出力 Synthesis 一定 再生 電力網 Solar 熱交換器 Grid 原子炉 Gas turbine 出力 +Wind ガスタービン 炉心 発電機 Time 前置冷却器 Nuclear plant power output 制御信号 冷却材 adjustment by gas pressure and Very炉心蓄熱の自動変調量 High Temperature: 370 MJ/oC Reactor (VHTR) turbine inertia. VHTR + RES hybrid system JAEA website: https://www.jaea.go.jp/04/o-arai/nhc/jp/research/intro/heat/heat_03.html [in Japanese] NICE Future Webinar, December 2018 21 Example of Hybrid system –electricity and heat- Decarbonized technology H2 Production Technology IS process decomposes water with heat of ca. 900oC using chemical reactions of iodine (I) and sulfur (S). High- o o H2 400 C temperature 900 C O2 heat Bunsen reaction (Production of H2 1/2O2 + 2HI hydrogen iodide H2SO4 + I2 and sulfuric acid) SO2 + H2O 2HI + H2SO4 SO2 I2 + SO2 + 2H2O + I2 H2O Water Decomposition of Decomposition of hydrogen iodide (HI) Sulfuric acid H2O JAEA website: https://www.jaea.go.jp/04/o-arai/nhc/en/research/intro/is/index.html NICE Future Webinar, December 2018 22 Effective Use of Uranium Resources for Sustainability Effective use of natural uranium can be provided by Closed fuel cycle and Fast reactors; thus ensuring energy security for several centuries. Scenarios: • IIASA/WEC-C2: “Ecologically-driven” scenario. Renewable energy and small reactor would be used as global warming countermeasures. • IEA ETP2015-2DS: Greenhouse gas would be reduced and sustainable energy systems would be used. • IAEA 2016 (High case): The current rates of economic and electricity demand growth, particularly in the Far East, would continue, and policy on the climate change would be shifted. • IAEA 2016 (Low case): Current market, technology, and resource trends would continue. Increase in nuclear output might not be achieved. NICE Future Webinar, December 2018 Y. Sagayama, “Generation IV Reactors,” Lecture at the university of Tokyo, Oct. 15, 2018. 23 Minimize radioactive waste by Gen-IV systems Burning and Transmutation of Pu and Minor Actinides by Fast Reactors GEN IV reactors and the ASTRID Project, P.
Recommended publications
  • WHAT WILL ADVANCED NUCLEAR POWER PLANTS COST? a Standardized Cost Analysis of Advanced Nuclear Technologies in Commercial Development
    WHAT WILL ADVANCED NUCLEAR POWER PLANTS COST? A Standardized Cost Analysis of Advanced Nuclear Technologies in Commercial Development AN ENERGY INNOVATION REFORM PROJECT REPORT PREPARED BY THE ENERGY OPTIONS NETWORK TABLE OF CONTENTS Executive Summary 1 1. Study Motivation and Objectives 6 Why Care about Advanced Nuclear Costs? 7 Origins of This Study 8 A Standardized Framework for Cost Analysis 8 2. Results 9 3. Study Methodology 14 EON Model 15 Company Preparedness and Strategies 19 Limits of This Analysis 20 Certainty Levels for Advanced Nuclear Cost Estimates 20 Realistic Considerations That May Influence Cost 21 4. Advanced Nuclear’s Design and Delivery Innovations 22 Context: The Cost of Conventional Nuclear 23 Design Considerations for Conventional Nuclear Reactors 24 Safety Enhancements of Advanced Nuclear 24 Overview of Reactor Designs 25 Delivery Issues with Conventional Nuclear Power 27 Innovations in the Delivery of Advanced Nuclear Technologies 28 Design Factors That Could Increase Advanced Nuclear Costs 30 5. Conclusions 31 6. References 32 Appendix A: Nuclear Plant Cost Categories 34 Appendix B: Operating Costs for a Nuclear Plant 35 Appendix C: Cost Category Details and Modeling Methodology 36 Appendix D: External Expert Review of Draft Report 43 THE FUTURE OF NUCLEAR TECHNOLOGY: A STANDARDIZED COST ANALYSIS EXECUTIVE SUMMARY Advanced nuclear technologies are controversial. Many people believe they could be a panacea for the world’s energy problems, while others claim that they are still decades away from reality and much more complicated and costly than conventional nuclear technologies. Resolving this debate requires an accurate and current understanding of the increasing movement of technology development out of national nuclear laboratories and into private industry.
    [Show full text]
  • Progress in Nuclear Energy 105 (2018) 83–98
    Progress in Nuclear Energy 105 (2018) 83–98 Contents lists available at ScienceDirect Progress in Nuclear Energy journal homepage: www.elsevier.com/locate/pnucene Technology perspectives from 1950 to 2100 and policy implications for the T global nuclear power industry Victor Nian Energy Studies Institute, National University of Singapore, Singapore ARTICLE INFO ABSTRACT Keywords: There have been two completed phases of developments in nuclear reactor technologies. The first phase is the Nuclear industry trends demonstration of exploratory Generation I reactors. The second phase is the rapid scale-up of Generation II Nuclear energy policy reactors in North America and Western Europe followed by East Asia. We are in the third phase, which is the ff Technology di usion construction of evolutionary Generation III/III+ reactors. Driven by the need for safer and more affordable New user state nuclear reactors post-Fukushima, the nuclear industry has, in parallel, entered the fourth phase, which is the International cooperation development of innovative Generation IV reactors. Through a comprehensive review of the historical reactor Advanced reactor development technology developments in major nuclear states, namely, USA, Russia, France, Japan, South Korea, and China, this study presents a projection on the future potentials of advanced reactor technologies, with particular focus on pressurized water reactors, high temperature reactors, and fast reactors, by 2100. The projected potentials provide alternative scenarios to develop insights that complement the established technology roadmaps. Findings suggest that there is no clear winner among these technologies, but fast reactors could demonstrate a new and important decision factor for emerging markets. Findings also suggest small modular reactors, espe- cially those belonging to Generation IV, as a transitional technology for developing domestic market and in- digenous technology competence for emerging nuclear states.
    [Show full text]
  • Fast-Spectrum Reactors Technology Assessment
    Clean Power Quadrennial Technology Review 2015 Chapter 4: Advancing Clean Electric Power Technologies Technology Assessments Advanced Plant Technologies Biopower Clean Power Carbon Dioxide Capture and Storage Value- Added Options Carbon Dioxide Capture for Natural Gas and Industrial Applications Carbon Dioxide Capture Technologies Carbon Dioxide Storage Technologies Crosscutting Technologies in Carbon Dioxide Capture and Storage Fast-spectrum Reactors Geothermal Power High Temperature Reactors Hybrid Nuclear-Renewable Energy Systems Hydropower Light Water Reactors Marine and Hydrokinetic Power Nuclear Fuel Cycles Solar Power Stationary Fuel Cells U.S. DEPARTMENT OF Supercritical Carbon Dioxide Brayton Cycle ENERGY Wind Power Clean Power Quadrennial Technology Review 2015 Fast-spectrum Reactors Chapter 4: Technology Assessments Background and Current Status From the initial conception of nuclear energy, it was recognized that full realization of the energy content of uranium would require the development of fast reactors with associated nuclear fuel cycles.1 Thus, fast reactor technology was a key focus in early nuclear programs in the United States and abroad, with the first usable nuclear electricity generated by a fast reactor—Experimental Breeder Reactor I (EBR-I)—in 1951. Test and/or demonstration reactors were built and operated in the United States, France, Japan, United Kingdom, Russia, India, Germany, and China—totaling about 20 reactors with 400 operating years to date. These previous reactors and current projects are summarized in Table 4.H.1.2 Currently operating test reactors include BOR-60 (Russia), Fast Breeder Test Reactor (FBTR) (India), and China Experimental Fast Reactor (CEFR) (China). The Russian BN-600 demonstration reactor has been operating as a power reactor since 1980.
    [Show full text]
  • Generation IV Nuclear Energy Systems: Ten-Year Program Plan
    GENERATION IV NUCLEAR ENERGY SYSTEMS TEN-YEAR PROGRAM PLAN Fiscal Year 2005 Volume I Released March 2005 Office of Advanced Nuclear Research DOE Office of Nuclear Energy, Science and Technology DISCLAIMER The Generation IV Nuclear Energy Systems Ten-Year Program Plan describes the updated system and crosscutting program plans that were in force at the start of calendar year 2005. However, the Generation IV research & development (R&D) plans continue to evolve, and this document will be updated annually or as needed. Even as this Program Plan is being released, several system R&D plans are still under development, most in collaboration with international, university, and industry partners. Consequently, the Program Plan should be viewed as a work in progress. For current information regarding this document or the plans described herein, please contact: David W. Ostby, Technical Integrator Generation IV program Idaho National Laboratory P.O. Box 1625 2525 N. Fremont Idaho Falls, ID 83415-3865 USA Tel: (208) 526-1288 FAX: (208) 526-2930 Email: [email protected] GENERATION IV NUCLEAR ENERGY SYSTEMS TEN-YEAR PROGRAM PLAN Fiscal Year 2005 Volume I March 2005 Idaho National Laboratory Idaho Falls, Idaho 83415 Prepared for the U.S. Department of Energy Office of Nuclear Energy Under DOE Idaho Operations Office Contract DE-AC07-05ID14517 i This page intentionally left blank. ii EXECUTIVE SUMMARY As reflected in the U.S. National Energy Policy [1], nuclear energy has a strong role to play in satisfying our nation's future energy security and environmental quality needs. The desirable environmental, economic, and sustainability attributes of nuclear energy give it a cornerstone position, not only in the U.S.
    [Show full text]
  • Generation IV Reactor Systems and Fuel Cycles (Horizon 2030): Technological Breakthroughs in Nuclear Fission (Int'l RD&DD)
    EUROPEAN COMMISSION RESEARCH DIRECTORATE-GENERAL Directorate J : ENERGY - EURATOM Unit 2 : Fission Generation IV reactor systems and fuel cycles (horizon 2030): technological breakthroughs in nuclear fission (int'l RD&DD) Georges VAN GOETHEM Innovation in Nuclear Fission, and Education & Training [email protected] EC DG RTD J2, Brussels, May 2008 Generation IV International Forum (GIF, 2001) VHTR SFR GFR SCWR LFR MSR 1 ABSTRACT Euratom signed in 2006 the Framework Agreement of the Generation IV International Forum (GIF). As a consequence, all Euratom actions in the area of innovative reactor systems are based on the four "Technology Goals for industry and society" set by the GIF: • sustainability: e.g. enhanced fuel utilisation and optimal waste management • economics: e.g. minimisation of costs of MWe installed and MWth generated • safety and reliability : e.g. robust safety architecture, enhanced EUR requirements • proliferation resistance and physical protection: e.g. impractical separation of Pu. To set the scene of Generation IV, the history of nuclear fission power is recalled with some discussion about the benefits and drawbacks of each previous Generation: • Generation I (1950 – 1970): Atoms-for-Peace era plants (4 countries concerned) • Generation II (1970 - 2000): safety and reliability (30 countries concerned) • Generation III (2000 - 2030): "evolutionary" steps to further improve safety (EUR) • Generation IV (horizon after 2030): "visionary" innovation regarding sustainability. Résumé Euratom a signé en 2006 l’Accord Cadre du GIF (« Generation IV International Forum »). Par conséquent, toutes les actions Euratom dans le domaine des systèmes réacteurs innovants sont basées sur les quatre «Objectifs technologiques pour l’industrie et la société»: • durabilité : par ex.
    [Show full text]
  • New Reactor Concepts for New Generation of Nuclear Power Plants in the Usa: an Overview
    Fifth Yugoslav Nuclear Society Conference YUNSC - 2004 ████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████████ NEW REACTOR CONCEPTS FOR NEW GENERATION OF NUCLEAR POWER PLANTS IN THE USA: AN OVERVIEW JASMINA VUJIĆ, EHUD GREENSPAN and MIODRAG MILOŠEVIĆ* Department of Nuclear Engineering, University of California, Berkeley, CA, USA [email protected], [email protected] *VINCA Institute of Nuclear Sciences, Belgrade, Serbian and Montenegro [email protected] ABSTRACT With the growing demands for more reliable energy sources, there is an international interest in the development of new nuclear energy systems to be deployed between 2010 and 2030, that will improve safety and reliability, decrease proliferation risks, improve radioactive waste management and lower cost of nuclear energy production. Six nuclear energy systems were selected as candidates for this Generation IV initiative. In this paper we will explore each of these concepts, as well as several of more advanced concepts. Key words: Generation IV, nuclear energy systems, non-proliferation 1. INTRODUCTION Just a few years ago, many analysts were projecting the decline of nuclear power. Reality has proven these projections to be wrong. The reasons for revival of nuclear energy are very clear: • nuclear plants have performed exceedingly well. As a group, U.S. nuclear utilities have improved the availability of their
    [Show full text]
  • Nordic Forum for Generation IV Reactors, Status and Activities in 2012
    NKS-270 ISBN 978-87-7893-343-0 Nordic Forum for Generation IV Reactors, Status and activities in 2012 Rudi Van Nieuwenhove1, Bent Lauritzen2, Erik Nonbøl2 1Institutt for Energiteknikk, OECD Halden Reactor Project, Norway 2Technical University of Denmark, DTU Nutech, Denmark December 2012 Abstract The Nordic-Gen4 (continuation from NOMAGE4) seminar was this year hosted by DTU Nutech at Risø, Denmark. The seminar was well attended (49 participants from 12 countries). The presentations covered many as- pects in Gen-IV reactor research and gave a good overview of the activi- ties within this field at the various institutes and universities. Participants had the possibility to visit the Danish Decommissioning site. Key words Nordic-Gen4, seminar, Risø NKS-270 ISBN 978-87-7893-343-0 Electronic report, December 2012 NKS Secretariat P.O. Box 49 DK - 4000 Roskilde, Denmark Phone +45 4677 4041 www.nks.org e-mail [email protected] Nordic-Gen4 activities 2012 Nordic Forum for Generation IV Reactors Status and activities in 2012 Rudi Van Nieuwenhove1, Bent Lauritzen2, Erik Nonbøl2 1Institutt for Energiteknikk OECD Halden Reactor Project Norway 2 Technical University of Denmark, DTU Nutech, Denmark TABLE OF CONTENTS 1. INTRODUCTION...................................................................................................................... 1 2. OBJECTIVES OF THE WORK ................................................................................................ 4 3. DELIVERABLES FOR 2012....................................................................................................
    [Show full text]
  • NKS-216, Nordic Nuclear Materials Forum for Generation IV Reactors
    Nordisk kernesikkerhedsforskning Norrænar kjarnöryggisrannsóknir Pohjoismainen ydinturvallisuustutkimus Nordisk kjernesikkerhetsforskning Nordisk kärnsäkerhetsforskning Nordic nuclear safety research NKS-216 ISBN 978-87-7893-286-0 Nordic Nuclear Materials Forum for Generation IV Reactors Clara Anghel (1) Sami Penttilä (2) (1) Studsvik Nuclear AB, Sweden (2) VTT, Finland March 2010 Abstract A network for material issues for Generation IV nuclear power has been initiated within the Nordic countries. The objectives of the Generation IV Nordic Nuclear Materials Forum (NOMAGE4) are to put the basis of a sustainable forum for Gen IV issues, especially focussing on fuels, cladding, structural materials and coolant interaction. Other issues include reactor physics, dynamics and diagnostics, core and fuel design. The present report summarizes the work performed during the year 2009. The efforts made include identification of organisations involved in Gen IV issues in the Nordic countries, update of the forum website, http://www.studsvik.se/GenerationIV, and investigation of capabilities for research within the area of Gen IV. Within the NOMAGE4 project a seminar on Generation IV Nuclear Energy Systems has been organized during 15-16th of October 2009. The aim of the seminar was to provide a forum for exchange of information, discussion on future research needs and networking of experts on Generation IV reactor concepts. As an outcome of the NOMAGE4, a few collaboration project proposals have been prepared/planned in 2009. The network was welcomed by the European Commission and was mentioned as an exemplary network with representatives from industries, universities, power companies and research institutes. NOMAGE4 has been invited to participate to the "European Energy Research Alliance, EERA, workshop for nuclear structural materials" http://www.eera- set.eu/index.php?index=41 as external observers.
    [Show full text]
  • Nuclear Data Needs for Generation IV Nuclear Energy Systems
    FRENCH ATOMIC ENERGY COMMISION (CEA) - NUCLEAR ENERGY DIVISION NuclearNuclear DataData NeedsNeeds forfor GenerationGeneration IVIV NuclearNuclear EnergyEnergy SystemsSystems G. Rimpault Commissariat à l’Energie Atomique (CEA) Cadarache Center 13108 Saint-Paul-lez-Durance Cedex, France [email protected] CEA/DER Cadarache Centre Gérald Rimpault Hotel Mascotte, 27 May 2004 • Aix en Provence, France 1 FRENCH ATOMIC ENERGY COMMISION (CEA) - NUCLEAR ENERGY DIVISION Generation IV Reactor Cores Six Reactor Concepts have been selected by the Generation IV International Forum (GIF) countries to meet challenging technology goals in four areas: Sustainability Economics Safety and reliability Proliferation resistance and physical protection. Among the six selected systems, 5 (SFR, GFR, LFR, SCWR, MSR) are fast systems while 3 (SCWR, MSR, VHTR) are thermal ones This implies some consequences on nuclear data needs CEA/DER Cadarache Centre Gérald Rimpault Hotel Mascotte, 27 May 2004 • Aix en Provence, France 2 FRENCH ATOMIC ENERGY COMMISION (CEA) - NUCLEAR ENERGY DIVISION Generic Nuclear Data Needs for Generation IV Reactor Cores Nuclear Data Needs for the six selected Generation IV systems should undergo a sensitivity analysis for selecting those data which are important But it must recognized straight from the beginning that evaluated nuclear data cannot as such meet the requirements especially for the fast systems Past experience should therefore be used. This will be done using experience •on SFR for the 5 (SFR, GFR, LFR, SCWR, MSR) and •on PWR for
    [Show full text]
  • Euratom Contribution to the Generation IV International Forum Systems in the Period 2005-2014 and Future Outlook
    Euratom Contribution to the Generation IV International Forum Systems in the period 2005-2014 and future outlook Joint Research Centre 2017 This publication is a Technical report by the Joint Research Centre (JRC), the European Commission’s science and knowledge service. It aims to provide evidence-based scientific support to the European policy-making process. The scientific output expressed does not imply a policy position of the European Commission. Neither the European Commission nor any person acting on behalf of the Commission is responsible for the use which might be made of this publication. Contact information Name: Andrea Bucalossi Address: Rue Champ de Mars 21 E-mail: [email protected] Tel.: 0032 29 88309 JRC Science Hub https://ec.europa.eu/jrc JRC104056 EUR 28391 EN PDF ISBN 978-92-79-64938-7 ISSN 1831-9424 doi:10.2760/256957 Print ISBN 978-92-79-64937-0 ISSN 1018-5593 doi:10.2760/875528 Luxembourg: Publications Office of the European Union, 2017 © European Union, 2017 The reuse policy of the European Commission is implemented by Commission Decision 2011/833/EU of 12 December 2011 on the reuse of Commission documents (OJ L 330, 14.12.2011, p. 39). Reuse is authorised, provided the source of the document is acknowledged and its original meaning or message is not distorted. The European Commission shall not be liable for any consequence stemming from the reuse. For any use or reproduction of photos or other material that is not owned by the EU, permission must be sought directly from the copyright holders.
    [Show full text]
  • Advanced Nuclear Reactors: Technology Overview and Current Issues
    Advanced Nuclear Reactors: Technology Overview and Current Issues April 18, 2019 Congressional Research Service https://crsreports.congress.gov R45706 SUMMARY R45706 Advanced Nuclear Reactors: Technology April 18, 2019 Overview and Current Issues Danielle A. Arostegui All nuclear power in the United States is generated by light water reactors (LWRs), which were Research Assistant commercialized in the 1950s and early 1960s and are now used throughout most of the world. LWRs are cooled by ordinary (“light”) water, which also slows (“moderates”) the neutrons that Mark Holt maintain the nuclear fission chain reaction. High construction costs of large conventional LWRs, Specialist in Energy Policy concerns about safety raised by the 2011 Fukushima nuclear disaster in Japan, and other issues have led to increased interest in unconventional, or “advanced,” nuclear technologies that could be less expensive and safer than existing LWRs. An “advanced nuclear reactor” is defined in legislation enacted in 2018 as “a nuclear fission reactor with significant improvements over the most recent generation of nuclear fission reactors” or a reactor using nuclear fusion (P.L. 115-248). Such reactors include LWR designs that are far smaller than existing reactors, as well as concepts that would use different moderators, coolants, and types of fuel. Many of these advanced designs are considered to be small modular reactors (SMRs), which the Department of Energy (DOE) defines as reactors with electric generating capacity of 300 megawatts and below, in contrast
    [Show full text]
  • The Challenge of Nuclear Reactor Structural Materials for Generation IV Nuclear Energy Systems
    20th International Conference on Structural Mechanics in Reactor Technology (SMiRT 20) Espoo, Finland, August 9-14, 2009 SMiRT 20-Division 10, Paper 1586 The Challenge of Nuclear Reactor Structural Materials for Generation IV Nuclear Energy Systems LI Chengliang, YANG Mengjia China Nuclear Power Design Company LTD. (Shengzhen) Shanghai Branch, Shanghai, China, e-mail:[email protected] Keywords: Generation IV Nuclear Energy Systems, Belt Zone, Structural Materials, Novel Alloy, Advanced Stainless Steels. 1 ABSTRACT (NO MORE THAN 200 WORDS) Generation IV Nuclear Energy Systems have been studied in the framework of the “Generation IV” International Forum, there can be little doubt that nuclear reactor structural materials technology, including: Selection, development and qualification, is one of the key issues to success of Gen Ⅳ Nuclear Energy Systems. By striving to meet this challenge, which is beyond the experience of the current nuclear power plants, the belt zone structural materials are required good resistance to irradiation damage, high thermal stress capacity, excellent resistance encompassing stress-corrosion cracking, and highly predictable responses to extreme levels, compatibility with Heat-Transfer media and other materials, very long-term stability enhanced in the system, adequate resources and easy fabrication as well as weld-ability, etc, to guarantee the security and integrity of the pressure boundary. This paper analyses and compares several materials under active consideration performance requirements, and also discusses candidate materials for use in different reactor components, which include various ferritic-martensitic steels, advanced austenitic stainless steels, nickel-base super-alloys, oxide-dispersion strengthened alloys, refractory alloys and etc. It is demonstrated that new materials, such as metals, carbides, nitrides, oxide, novel alloy, solid solutions or composites focuses on higher stability and better mechanical performances.
    [Show full text]