WHAT WILL ADVANCED NUCLEAR POWER PLANTS COST? a Standardized Cost Analysis of Advanced Nuclear Technologies in Commercial Development
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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. -
A Comparison of Advanced Nuclear Technologies
A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D MARCH 2017 B | CHAPTER NAME ABOUT THE CENTER ON GLOBAL ENERGY POLICY The Center on Global Energy Policy provides independent, balanced, data-driven analysis to help policymakers navigate the complex world of energy. We approach energy as an economic, security, and environmental concern. And we draw on the resources of a world-class institution, faculty with real-world experience, and a location in the world’s finance and media capital. Visit us at energypolicy.columbia.edu facebook.com/ColumbiaUEnergy twitter.com/ColumbiaUEnergy ABOUT THE SCHOOL OF INTERNATIONAL AND PUBLIC AFFAIRS SIPA’s mission is to empower people to serve the global public interest. Our goal is to foster economic growth, sustainable development, social progress, and democratic governance by educating public policy professionals, producing policy-related research, and conveying the results to the world. Based in New York City, with a student body that is 50 percent international and educational partners in cities around the world, SIPA is the most global of public policy schools. For more information, please visit www.sipa.columbia.edu A COMPARISON OF ADVANCED NUCLEAR TECHNOLOGIES Andrew C. Kadak, Ph.D* MARCH 2017 *Andrew C. Kadak is the former president of Yankee Atomic Electric Company and professor of the practice at the Massachusetts Institute of Technology. He continues to consult on nuclear operations, advanced nuclear power plants, and policy and regulatory matters in the United States. He also serves on senior nuclear safety oversight boards in China. He is a graduate of MIT from the Nuclear Science and Engineering Department. -
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. -
Breakthrough Institute How to Make Nuclear Cheap
HOW TO MAKE NUCLEAR CHEAP July 2013 SAFET Y, READINESS, MODULARIT Y, and EFFICIENCY TED NORDHAUS, JESSICA LOVERING, AND MICHAEL SHELLENBERGER HOW TO MAKE NUCLEAR CHEAP SAFETY, READINESS, MODULARITY, and EFFICIENCY TED NORDHAUS, JESSICA LOVERING, AND MICHAEL SHELLENBERGER THE BREAKTHROUGH INSTITUTE | JULY 2013 ACKNOWLEDGMENTS The Breakthrough Institute would like to thank the following people for their contri - bu tions to this report. All opinions expressed herein are those of the Break through Institute and do not necessarily reflect the opinions of the individuals below. Joseph Chaisson, Research and Technical Director, Clean Air Task Force Armond Cohen, Executive Director, Clean Air Task Force Ashley Finan, Senior Project Manager for Energy Innovation, Clean Air Task Force Richard Lester, Japan Steel Industry Professor and Head of the Department of Nuclear Science and Engineering at the Massachusetts Institute of Technology Mark Lynas, journalist and visiting research associate, Oxford University’s School of Geography and the Environment Charles Peterson, Partner, Energy Section, Pillsbury Law Per Peterson, William and Jean McCallum Floyd Endowed Chair, Department 4 of Nuclear Engineering, University of California, Berkeley Burton Richter, Paul Pigott Professor in the Physical Sciences, Stanford University, and Director Emeritus at the Stanford Linear Accelerator Center Ray Rothrock, Partner, Venrock Jim Swartz, Accel Partners Special thanks to Brian Sergi for preliminary research performed during the 2012 Breakthrough Generation Fellowship program. About the Authors Ted Nordhaus and Michael Shellenberger are cofounders of the Breakthrough Institute, where they are Chairman and President, respectively. They are coauthors of Break Through: From the Death of Environmentalism to the Politics of Possibility as well as dozens of essays and reports on energy, climate change, and the environment. -
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. -
Preliminary Quantitative Feasibility Analysis of Proposed Thorium-Based Nuclear Reactor
IOP Conference Series: Materials Science and Engineering PAPER • OPEN ACCESS Preliminary quantitative feasibility analysis of proposed Thorium-based nuclear reactor To cite this article: Anas Muhamad Pauzi et al 2019 IOP Conf. Ser.: Mater. Sci. Eng. 555 012006 View the article online for updates and enhancements. This content was downloaded from IP address 43.130.79.121 on 08/10/2021 at 08:30 International Nuclear Science, Technology and Engineering Conference 2018 IOP Publishing IOP Conf. Series: Materials Science and Engineering 555 (2019) 012006 doi:10.1088/1757-899X/555/1/012006 Preliminary quantitative feasibility analysis of proposed Thorium-based nuclear reactor Anas Muhamad Pauzi1,a), Azril Wasim Abdul Wahid1, Juniza Md Saad1 1College of Engineering, Universiti Tenaga Nasional, Jalan IKRAM-UNITEN, 43000 Kajang, Selangor, Malaysia [email protected] Abstract. In the beginning of the 21st century, several research institutions and also private companies had proposed various design of thorium-based nuclear reactor, ranging from solid fuel to molten fuel, fast and thermal neutron spectrum and also various path of waste management. This paper studies 10 of the proposed reactor designs by 10 different organizations, three key aspects analysed quantitatively namely price per kilowatt, safety features and spent fuel managements. Corresponding factors contributing to the key aspects mentioned above were gathered, weighted based on evidence available and analysed using decision matrix. Based on the information collected, preliminary ranking were constructed based on trends between various factors. 1. Introduction 1.1. Thorium reactor developer of the 21st century Thorium fuel reactor was first developed by the Oak Ridge National Laboratory (ORNL) in 1950s, under the Aircraft Reactor Experimental (ARE) by Alvin Weinberg, then director of ORNL. -
Two-Dimensional Neutronic and Fuel Cycle Analysis of the Transatomic Power Molten Salt Reactor
ORNL/TM-2016/742 Two-Dimensional Neutronic and Fuel Cycle Analysis of the Transatomic Power Molten Salt Reactor Benjamin R. Betzler, ORNL Jeffrey J. Powers, ORNL Andrew Worrall, ORNL Sean Robertson, TAP Leslie Dewan, TAP Mark Massie, TAP Approved for public release. Distribution is unlimited. January 15, 2017 DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via US Department of Energy (DOE) SciTech Connect. Website: http://www.osti.gov/scitech/ Reports produced before January 1, 1996, may be purchased by members of the public from the following source: National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone: 703-605-6000 (1-800-553-6847) TDD: 703-487-4639 Fax: 703-605-6900 E-mail: [email protected] Website: http://www.ntis.gov/help/ordermethods.aspx Reports are available to DOE employees, DOE contractors, Energy Technology Data Ex- change representatives, and International Nuclear Information System representatives from the following source: Office of Scientific and Technical Information PO Box 62 Oak Ridge, TN 37831 Telephone: 865-576-8401 Fax: 865-576-5728 E-mail: [email protected] Website: http://www.osti.gov/contact.html This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal lia- bility or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or rep- resents that its use would not infringe privately owned rights. -
“Advanced” Isn't Always Better
SERIES TITLE OPTIONAL “Advanced” Isn’t Always Better Assessing the Safety, Security, and Environmental Impacts of Non-Light-Water Nuclear Reactors “Advanced” Isn’t Always Better Assessing the Safety, Security, and Environmental Impacts of Non-Light-Water Nuclear Reactors Edwin Lyman March 2021 © 2021 Union of Concerned Scientists All Rights Reserved Edwin Lyman is the director of nuclear power safety in the UCS Climate and Energy Program. The Union of Concerned Scientists puts rigorous, independent science to work to solve our planet’s most pressing problems. Joining with people across the country, we combine technical analysis and effective advocacy to create innovative, practical solutions for a healthy, safe, and sustainable future. This report is available online (in PDF format) at www.ucsusa.org/resources/ advanced-isnt-always-better and https:// doi.org/10.47923/2021.14000 Designed by: David Gerratt, Acton, MA www.NonprofitDesign.com Cover photo: Argonne National Laboratory/Creative Commons (Flickr) Printed on recycled paper. ii union of concerned scientists [ contents ] vi Figures, Tables, and Boxes vii Acknowledgments executive summary 2 Key Questions for Assessing NLWR Technologies 2 Non-Light Water Reactor Technologies 4 Evaluation Criteria 5 Assessments of NLWR Types 8 Safely Commercializing NLWRs: Timelines and Costs 9 The Future of the LWR 9 Conclusions of the Assessment 11 Recommendations 12 Endnotes chapter 1 13 Nuclear Power: Present and Future 13 Slower Growth, Cost and Safety Concerns 14 Can Non-Light-Water Reactors -
Utah Thorium Energy and Medical Isotopes
Utah Thorium Energy and Medical Isotopes Dr. Matthew J Memmott Brigham Young University November 16th 2016 2 Utah Winters… 3 Why Nuclear? • Massive Energy – 10,000,000 times chemical – 1 Uranium Pellet ( 7 gm): • 3.5 barrels of oil • 17,000 scf natural gas • 1800 lbs coal – Reliable • ~92% Capacity factor – Clean – No emissions! – Medicine • 99Mo, 131I, etc. – only come from nuclear reactors! 4 Widespread Uses • Medicine • 20M procedures a year in US – X-rays – Cancer Treatments – Diagnostics (PET, MRI, CTS) • Energy • 20% of the US electricity • No emissions • Lowest Death Rate Annual Death rates per TW*hr US Electricity • Reliable – runs 343 days/year Source Deaths Percentage Coal 161 39% Oil 36 1% • Research Natural Gas 4 27% Biofuel/Biomass 12 1.70% • Manufacturing Solar 0.83 0.40% Wind 0.15 4.40% Hydro 1.4 6% Nuclear 0.04 20% 5 Targeted Alpha Therapy 6 Two Nuclear Pathways • Light Water Reactor – Modified sub reactor – Requires lots of water – Pressurized – Weapons path - Pu • Molten Salt Reactor – No solid fuel – No high pressure – Coolant is Fl-Li-Be – No Weapons – 5-10 years operation 7 Molten Salt Reactor • Silicone chip vs. vacuum tube • 800+ ˚C • 44% efficiency • Medical isotopes AND electricity concurrently • Solves 3 nuclear problems 8 Safety 9 Waste 10 Reduce Proliferation Risk • Must produce (and gather) 241Pu, 239Pu, 235U, or 233U – 241Pu, 239Pu are never formed – 235U in very small amounts, rapidly fissioned – Lots of 233U, but • 233U is mixed with 232U • 232U is active gamma emitter • Gammas ruin bombs: – Harmful to handle -
History, Background, and Current MSR Developments
Module 1: History, Background, and Current MSR Developments Presentation on Molten Salt Reactor Technology by: David Holcomb, Ph.D. Advanced Reactor Systems and Safety Reactor and Nuclear Systems Division Presentation for: US Nuclear Regulatory Commission Staff Washington, DC Date: November 7–8, 2017 ORNL is managed by UT-Battelle for the US Department of Energy Summary of Modules • Module 1 – History, Background, and Current MSR Developments – Introduction to MSRs, early development, current developers • Module 2 – Overview of MSR Technology and Concepts – System overviews, technical maturity • Module 3 – Overview of Fuel and Coolant Salt Chemistry and Thermal Hydraulics – Salt properties and characteristics • Module 4 – MSR Neutronics – Comparison with LWRs, reactivity feedback, challenges 2 Module 1 History, Background, and Current MSR Developments Summary of Modules (cont.) • Module 5 – Materials – Requirements, options, challenges • Module 6 – Systems and Components – Nuclear heat supply, heat transport, support systems, balance of plant • Module 7 – Overview of MSR Instrumentation – Key process parameters, support for automation, tritium monitoring, fissile material tracking • Module 8 – Fuel Cycle and Safeguards – Reactor technology, neutron spectrum, fundamental concepts 3 Module 1 History, Background, and Current MSR Developments Summary of Modules (cont.) • Module 9 – Operating Experience – Corrosion studies, OpE issues, remote handling, long-term storage • Module 10 – Safety Analysis and Design Requirements – MSR events, accident -
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