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WASH 1097 UC-80 THE USE OF THORIUM IN NUCLEAR POWER REACTORS JUNE 1969 PREPARED BY Brookhaven National Laboratory AND THE Division of Reactor Development and Technology WITH THE ASSISTANCE OF ARGONNE NATIONAL LABORATORY BABCOCK & WILCOX GULF GENERAL ATOMIC OAK RIDGE NATIONAL LABORATORY PACIFIC NORTHWEST LABORATORY For sale by the Superintendent of Documents, U.S. Government Printing Office Washington, D.C. 20402 - Price $1.25 FOREWORD This report on "The Use of Thorium in Nuclear Power Reactors" was prepared under the direction of the Division of Reactor Development and Technology, U.S.A.E.C., as part of an overall assessment of the Civilian Nuclear Power Program initiated in response to a request in 1966 by the Joint Committee on Atomic Energy. It represents the results of the inquiry by the Thorium Systems Task Force whose membership included representatives of Babcock & Wilcox Company, Gulf General Atomic Company, the Argonne National Laboratory, the Brookhaven National Laboratory, the Oak Ridge National Laboratory, the Pacific Northwest Laboratory, and the U.S. Atomic Energy Commission. Publication of this report, which provides information basic to the AEC reactor development program, completes one phase of the evaluation effort outlined in the 1967 Supplement to the 1962 Report to the President on Civilian Nuclear Power, issued in February 1967. The 1967 Supplement outlined changes since 1962 in the technical, economic and resource picture and provided background for further study. Specifically, this report represents the consensus of the task force on the potential use of the thorium cycle and the specific thorium fueled reactor designs which have been proposed. -
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. -
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. -
An Introduction to Nuclear Power – Science, Technology and UK
sustainable development commission The role of nuclear power in a low carbon economy Paper 1: An introduction to nuclear power – science, technology and UK policy context An evidence-based report by the Sustainable Development Commission March 2006 Table of contents 1 INTRODUCTION ................................................................................................................................. 3 2 ELECTRICITY GENERATION ................................................................................................................. 4 2.1 Nuclear electricity generation ................................................................................................. 4 2.2 Fission – how does it work?..................................................................................................... 4 2.3 Moderator ................................................................................................................................. 5 2.4 Coolant...................................................................................................................................... 5 2.5 Radioactivity ............................................................................................................................. 6 3 THE FUEL CYCLE: FRONT END ............................................................................................................ 7 3.1 Mining and milling ................................................................................................................... 7 3.2 Conversion and -
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. -
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. -
Nuclear Fuels and Reprocessing Technologies: a US Perspective
INL/EXT-20-59106 Review – Nuclear Fuels and Reprocessing Technologies: A U.S. Perspective March 2021 Guy Fredrickson Tae-Sic Yoo DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof. INL/EXT-20-59106 Review – Nuclear Fuels and Reprocessing Technologies: A U.S. Perspective Guy Fredrickson Tae-Sic Yoo March 2021 Idaho National Laboratory Pyrochemistry & Molten Salt Systems Department Idaho Falls, Idaho 83415 http://www.inl.gov Prepared for the U.S. Department of Energy Office of Nuclear Energy Under DOE Idaho Operations Office Contract DE-AC07-05ID14517 Page intentionally left blank ABSTRACT Reprocessing and/or waste management issues are of concern to the “back end” of the nuclear fuel cycle. Of course, there are a great many “nuclear fuel cycle” scenarios to consider; if not in practice, then at least in theory. The simplest conceptually is the “once through” fuel cycle in which the spent fuel is discarded. -
NRC Collection of Abbreviations
I Nuclear Regulatory Commission c ElLc LI El LIL El, EEELIILE El ClV. El El, El1 ....... I -4 PI AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources: 1. The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2. The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 3. The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica- tions, it is not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence; Commission papers; and applicant and licensee docu- ments and correspondence. The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro- ceedings, international agreement reports, grantee reports, and NRC booklets and bro- chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula- tions, and Nuclear Regulatory Commission Issuances. Documents available from the National Technical Information Service Include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. -
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. -
Identifying Preliminary Criteria for Safeguarding Advanced Nuclear Reactors
A. NILSSON et al. IDENTIFYING PRELIMINARY CRITERIA FOR SAFEGUARDING ADVANCED NUCLEAR REACTORS A. NILSSON AN & Associates Uppsala, Sweden [email protected] C. JORANT SDRI Consulting Paris, France [email protected] A. FINAN Nuclear Innovation Alliance Cambridge, MA, USA [email protected] E. REDMOND Nuclear Energy Institute Washington, DC, USA [email protected] K. LUONGO Partnership for Global Security Washington, DC, USA [email protected] Abstract Climate change and the urgent need to reduce carbon emission globally forecast a significant rise in the interest of advanced nuclear reactors. The contributed paper presents the results of a dedicated study of proliferation resistance of the main technologies for advanced nuclear reactors. Much of the current safeguards system has been developed and implemented for the water-cooled reactors that dominate the nuclear energy landscape. Advanced nuclear reactors are distinctly different compared with light-water reactors, with the use of different coolants and a broader spectrum of fuel compositions. Some advanced reactor designs employ a fast neutron spectrum, often associated with an ability to create plutonium. The variety of advanced reactor designs and their coolants present challenges to the existing safeguards regime. Some of the designs allow for on-line fuel processing and unique refuelling schemes. These features may require updated or new tools for nuclear accountancy and control as well as built-in technological features to prevent malicious use of the facility. The paper communicates the results of an overview of the most prominent advanced nuclear reactor designs, in which their proliferation resistance is assessed in comparison with the implementation of IAEA safeguards at a light water-cooled reactor (LWR) fuelled with low enriched Uranium, as established in States with comprehensive safeguards agreements and additional protocols. -
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 -
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....................................................................................................