Nuclear Energy of the Future: What Research for Which Objectives?
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Developing an Intergovernmental Nuclear Regulatory Organization
Developing an Intergovernmental Nuclear Regulatory Organization: Lessons Learned from the International Civil Aviation Organization, the International Maritime Organization, and the International Telecommunication Union Clarence Eugene Carpenter, Jr. Bachelor of Science in Mechanical Engineering, May 1988 Seattle University, Seattle, WA Master of Science in Technical Management, May 1997 The Johns Hopkins University, Baltimore, MD Master of Arts in International Science and Technology Policy, May 2009 The George Washington University, Washington, DC A Dissertation submitted to The Faculty of The Columbian College of Arts and Sciences of The George Washington University in partial fulfillment of the requirements for the degree of Doctor of Philosophy January 10, 2020 Dissertation directed by Kathryn Newcomer Professor of Public Policy and Public Administration The Columbian College of Arts and Sciences of The George Washington University certifies that Clarence Eugene Carpenter, Jr. has passed the Final Examination for the degree of Doctor of Philosophy as of November 26, 2019. This is the final and approved form of the dissertation. Developing an Intergovernmental Nuclear Regulatory Organization: Lessons Learned from the International Civil Aviation Organization, the International Maritime Organization, and the International Telecommunication Union Clarence Eugene Carpenter, Jr. Dissertation Research Committee: Kathryn Newcomer, Professor of Public Policy and Public Administration, Dissertation Director Philippe Bardet, Assistant Professor, -
KERNFORSCHUNGSANLA JULICH Gmbh
KERNFORSCHUNGSANLA JULICH GmbH Proceedings of the Workshop on Structural Design Criteria for HTR Jiilich, 31. January - 1. February 1989 Editors: G. Breitbach F. Schubert H. Nickel Jiil-Conf-71 April 1989 ISSN 0344-5798 Als Manuskript gedruckt Berichte der Kernforschungsanlage Jülich - Jül-Conf-71 Zu beziehen durch: ZENTRALBIBLIOTHEK der Kernforschungsanlage Jülich GmbH Postfach 1913 • D-5170 Jülich (Bundesrepublik Deutschland) Telefon: 02461/610 • Telex: 833556-0 kf d Proceedings of the Workshop on Structural Design Criteria for HTR Jiilich, 31. January - 1. February 1989 Editors: G. Breitbach F. Schubert H. Nickel Workshop on Structural Design Criteria for HTR Introductural remarks Most of the presentations given in this workshop are based on the German research and development project "HTR Design Criteria" carried out under the sponsorship of the Federal Ministry of Research and Technology. The main emphasis of this work was to acquire the fundamental principles and basic data for the establishment of German KTA-rules (KTA: Nuclear Safety Standards Commission) for the design of HTR-structural components. The project began in 1984 and the research work divided among several working groups and task forces, with participation from several institutions and companies. The role of coordination has been carried out by the Institute for Reactor Materials, Nuclear Research Centre Julien, headed by Prof. Dr. H. Nickel. The work has been organized into four working groups: a) Technical safety boundary conditions; b) Metallic structural components; c) Prestressed concrete pressure vessel; d) Graphitic structural components. The required work in each group was divided between a number of task forces. The membership of each group and task force is given in the appendix. -
2012/054167 Al
(12) INTERNATIONAL APPLICATION PUBLISHED UNDER THE PATENT COOPERATION TREATY (PCT) (19) World Intellectual Property Organization International Bureau (10) International Publication Number (43) International Publication Date _ . 26 April 2012 (26.04.2012) 2012/054167 Al (51) International Patent Classification: (74) Agent: SEYMOUR, Michael, J.; Babcock & Wilcox G21C 3/334 (2006.01) G21C 3/32 (2006.01) Nuclear Energy, Inc., Law Dept - Intellectual Property, 20 South Van Buren Avenue, Barberton, OH 44203 (US). (21) International Application Number: PCT/US201 1/052495 (81) Designated States (unless otherwise indicated, for every kind of national protection available): AE, AG, AL, AM, (22) International Filing Date: AO, AT, AU, AZ, BA, BB, BG, BH, BR, BW, BY, BZ, 2 1 September 201 1 (21 .09.201 1) CA, CH, CL, CN, CO, CR, CU, CZ, DE, DK, DM, DO, (25) Filing Language: English DZ, EC, EE, EG, ES, FI, GB, GD, GE, GH, GM, GT, HN, HR, HU, ID, IL, IN, IS, JP, KE, KG, KM, KN, KP, (26) Publication Language: English KR, KZ, LA, LC, LK, LR, LS, LT, LU, LY, MA, MD, (30) Priority Data: ME, MG, MK, MN, MW, MX, MY, MZ, NA, NG, NI, 12/909,252 2 1 October 2010 (21 .10.2010) US NO, NZ, OM, PE, PG, PH, PL, PT, QA, RO, RS, RU, RW, SC, SD, SE, SG, SK, SL, SM, ST, SV, SY, TH, TJ, (71) Applicant (for all designated States except US): BAB- TM, TN, TR, TT, TZ, UA, UG, US, UZ, VC, VN, ZA, COCK & WILCOX NUCLEAR ENERGY, INC. [US/ ZM, ZW. US]; 800 Main Street, Lynchburg, VA 24504 (US). -
Nuclear and Energy Independence
Meetings ANS WINTER MEETING Nuclear and energy independence HILE ORGANIZATIONS HAVE canceled or altered conferences in W the wake of the events of Sep- Major themes of the plenary: tember 11, the American Nuclear Society at- tracted more than 1100 attendants to its Win- N ter Meeting in November in Reno, Nev. “In H2 power can be an application light of recent events, that is a remarkable ac- complishment,” ANS President Gail Marcus of nuclear commented during the opening plenary. The large gathering was due perhaps to the upbeat mood of the industry in general, thanks N 50 years since first electricity with EBR-I in part to the Bush administration’s support of the continued use and further deployment of N nuclear power, and because any hope for re- A proposal for a continental supergrid ducing greenhouse gas emissions likely would include nuclear power in a national energy policy. oring the EBR-I and the nuclear pioneers who was associate project director of the EBR-I During the plenary Marcus paraphrased developed it. The proclamation recognized the and project manager for another reactor, the Charles Dickens by saying, “It is the best of environmental benefits of nuclear power and EBR-II. He later became director of the Re- times, it is the worst of times,” in reference feted those who worked to provide the world actor Engineering Division at Argonne Na- to the terrorist attacks on the United States with “clean, sustainable energy for the bene- tional Laboratory before moving on to Illinois and the opportunity for nuclear power to fit of humankind for centuries by making use Power Company. -
HTGR Dust Safety Issues and Needs for Research and Development
INL/EXT-11-21097 HTGR Dust Safety Issues and Needs for Research and Development P. W. Humrickhouse June 2011 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, trade mark, 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-11-21097 HTGR Dust Safety Issues and Needs for Research and Development P. W. Humrickhouse June 2011 Idaho National Laboratory Next Generation Nuclear Plant Project 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 ABSTRACT This report presents a summary of high temperature gas-cooled reactor dust safety issues. It draws upon a literature review and the proceedings of the Very High Temperature Reactor Dust Assessment Meeting held in Rockville, MD in March 2011 to identify and prioritize the phenomena and issues that characterize the effect of carbonaceous dust on high temperature reactor safety. -
Reactor Technology Safety and Siting
XA0101477-5/I5* IAEA-TC-389.26 LIMITED DISTRIBUTION REACTOR TECHNOLOGY SAFETY AND SITING REPORT OF A TECHNICAL COMMITTEE MEETING ORGANIZED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY AND HELD IN DIMITROVGRAD, USSR, 21-23 JUNE 1989 Reproduced by the IAEA Vienna, Austria, 1990 NOTE The material in this document has been supplied by the authors and has not been edited by the IAEA. The views expressed remain the responsibility of the named authors and do not necessarily reflect those of the govern- ments) of the designating Member State(s). In particular, neither the IAEA nor any other organization or body sponsoring this meeting can be held responsible for any material reproduced in this document. FOREWORD On the invitation of the Government of the Union of Soviet Socialist Republics, the Eleventh International Conference on the HTGR and the IAEA Technical Committee Meeting on Gas-Cooled Reactor Technology, Safety and Siting were held in Dimitrovgrad, USSR, on June 21-23, 1989. The meetings complemented each other. Due to the large worldwide interest, the conference attracted approximately 60 participants from 18 countries and 130 Soviet delegates. About 50 foreign participants and 100 Soviet delegates stayed over for the Technical Committee Meeting. The Technical Committee Meeting provided the Soviet delegates with an opportunity to display the breadth of their program on HTGR's to an international audience. Nearly one-half of the papers were presented by Soviet participants. Among the highlights of the meeting were the following: - The diverse nature and large magnitude of the Soviet research and development program on high temperature gas-cooled reactors. -
Deployability of Small Modular Nuclear Reactors for Alberta Applications Report Prepared for Alberta Innovates
PNNL-25978 Deployability of Small Modular Nuclear Reactors for Alberta Applications Report Prepared for Alberta Innovates November 2016 SM Short B Olateju (AI) SD Unwin S Singh (AI) A Meisen (AI) DISCLAIMER NOTICE This report was prepared under contract with the U.S. Department of Energy (DOE), as an account of work sponsored by Alberta Innovates (“AI”). Neither AI, Pacific Northwest National Laboratory (PNNL), DOE, the U.S. Government, nor any person acting on their behalf makes any warranty, express 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. Reference 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 AI, PNNL, DOE, or the U.S. Government. The views and opinions of authors expressed herein do not necessarily state or reflect those of AI, PNNL, DOE or the U.S. Government. Deployability of Small Modular Nuclear Reactors for Alberta Applications SM Short B Olateju (AI) SD Unwin S Singh (AI) A Meisen (AI) November 2016 Prepared for Alberta Innovates (AI) Pacific Northwest National Laboratory Richland, Washington 99352 Executive Summary At present, the steam requirements of Alberta’s heavy oil industry and the Province’s electricity requirements are predominantly met by natural gas and coal, respectively. On November 22, 2015 the Government of Alberta announced its Climate Change Leadership Plan to 1) phase out all pollution created by burning coal and transition to more renewable energy and natural gas generation by 2030 and 2) limit greenhouse gas (GHG) emissions from oil sands operations. -
Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors
0 Department of Nuclear Engineering And Radiation Health Physics DESIGN AND ANALYSIS OF A NUCLEAR REACTOR CORE FOR INNOVATIVE SMALL LIGHT WATER REACTORS. By Alexey I. Soldatov A DISSERTATION Submitted to Oregon State University March 9, 2009 1 AN ABSTRACT OF THE DISSERTATION OF Alexey I. Soldatov for the degree of Doctor of Philosophy in Nuclear Engineering presented on March 9, 2009. Title: Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors. Abstract approved: Todd S. Palmer In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design issues related with increased fuel enrichment (8.0%) and specific MASLWR operational conditions (such as lower operational pressure and temperature, and increased leakage due to small core). Neutron physics calculations are performed with the commercial nuclear industry tools CASMO-4 and SIMULATE-3, developed by Studsvik Scandpower Inc. The first set of results are generated from infinite lattice level calculations with CASMO-4, and focus on evaluation of the principal differences between standard PWR fuel and MASLWR fuel. Chapter 4-1 covers aspects of fuel isotopic composition changes with burnup, evaluation of kinetic parameters and reactivity coefficients. Chapter 4-2 discusses gadolinium self-shielding and shadowing effects, and subsequent impacts on power generation peaking and Reactor Control System shadowing. 2 The second aspect of the research is dedicated to core design issues, such as reflector design (chapter 4-3), burnable absorber distribution and programmed fuel burnup and fuel use strategy (chapter 4-4). -
Appendix C October 8, 2014
Nuclear Fuel Cycle Evaluation and Screening – Final Report – Appendix C October 8, 2014 APPENDIX C EVALUATION CRITERIA AND METRICS Nuclear Fuel Cycle Evaluation and Screening – Final Report – Appendix C ii October 8, 2014 Nuclear Fuel Cycle Evaluation and Screening – Final Report – Appendix C October 8, 2014 iii CONTENTS C. Evaluation Criteria and Metrics ......................................................................................................... 1 C-1. Nuclear Waste Management Criterion ..................................................................................... 1 C-1.1 Background on Nuclear Waste Management .............................................................. 1 C-1.2 Metric Development for the Nuclear Waste Management Criterion .......................... 5 C-1.3 Mass of SNF+HLW Disposed per Energy Generated ................................................ 6 C-1.4 Activity of SNF+HLW (@100 years) per Energy Generated ..................................... 7 C-1.5 Activity of SNF+HLW (@100,000 years) per Energy Generated .............................. 7 C-1.6 Mass of DU+RU+RTh Disposed per Energy Generated ............................................ 8 C-1.7 Volume of LLW per Energy Generated ...................................................................... 9 References for C-1. ........................................................................................................................... 25 C-2. Proliferation Risk Criterion ................................................................................................... -
The French Approach for the Regulation of Research Reactors
The French approach for the regulation of research reactors D. Conte, A. Chevallier Autorité de sûreté nucléaire, Paris, France Abstract. The French Nuclear Safety Authority (ASN) regulates civil nuclear facilities in France. In addition to the pool of 58 pressurized water reactors ASN also regulates several research reactors which are all unique installations. The regulatory approach for research reactors takes cognisance of the different level of hazard encountered in their operation and hence requires a different approach to the management of safety in comparison with nuclear power reactor operations. For a number of years, ASN has been striving to optimise its regulation of experimental reactors. To ensure the optimum level of safety by focusing on the most important safety issues and allowing the licensee to exercise its full responsibilities through the use of internal authorisations. The internal authorisations system, which has been in operation for several years now with a number of experimental reactors, is designed to achieve this two-fold objective. In addition to the careful use of a new range of tools for its regulatory framework in the research reactors area, ASN has other safety challenges for example the ageing of most of the existing facilities and the licensing of new reactors with a high international profile such as the Jules Horowitz reactor or the ITER fusion reactor. 1. Introduction The French Nuclear Safety Authority (ASN) regulates civil nuclear facilities in France (164). In addition to the pool of 58 pressurized water reactors ASN also regulates research reactors which are all unique installations. Most of the research reactors are operated by the atomic energy commission (CEA). -
Sensitivity and Uncertainty Analysis of Multiphysics Nuclear Reactor Core Depletion
SENSITIVITY AND UNCERTAINTY ANALYSIS OF MULTIPHYSICS NUCLEAR REACTOR CORE DEPLETION by Andrew Scott Bielen A dissertation submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy (Nuclear Engineering and Radiological Sciences) in the University of Michigan 2015 Doctoral Committee: Professor Thomas J. Downar , Co-Chair Associate Professor Annalisa Manera, Co-Chair Associate Professor Krzysztof J. Fidkowski Professor John C. Lee Joseph L. Staudenmeier, US Nuclear Regulatory Commission For my wife, Lisa ii AKNOWLEDGEMENTS I would like to acknowledge the contributions of the many that helped and guided me through this Ph.D. process. First and foremost are my co-advisors Prof. Tom Downar and Prof. Annalisa Manera, whose guidance and support were instrumental in the completion of this dissertation. I would also like to thank my committee members, Prof. John Lee and Prof. Krzysztof Fidkowski, and Dr. Joe Staudenmeier of the US Nuclear Regulatory Commission, whose feedback on this dissertation was invaluable. Additionally, I thank my branch chief at the NRC, Dr. Chris Hoxie, for his patience, understanding, and support during the completion of this work. In addition to these members, I must also thank the following: Dr. Patrick Raynaud of the US NRC and Ken Geelhood of Pacific Northwest National Laboratory, for conversations and guidance on working with and developing the FRAPCON fuel performance code for coupled neutronics and uncertainty analysis was crucial; Dr. Andrew Ward of the University of Michigan, for assisting me with the necessary PARCS/PATHS development and cross section generation using HELIOS; Dr. Tim Drzewiecki of the US NRC for assistance in providing the computer resources required to complete the sensitivity and uncertainty portion of this thesis; and Michael Rose and Thomas Saller at the University of Michigan for supporting me on my visits back to Ann Arbor. -
Nuclear Energy and the Three Mile Island Unit Two Accident Lesson Plans and Resource Guide
Nuclear Energy and the Three Mile Island Unit Two Accident Lesson Plans and Resource Guide © 2009 EFMR Monitoring Group, Inc. 4100 Hillsdale Road, Harrisburg, PA 17112 www.efmr.org 1 Nuclear Energy and the Three Mile Island Unit Two Accident Lesson Plans and Resource Guide © 2009 EFMR Monitoring Group, Inc. 4100 Hillsdale Road Harrisburg, PA 17112 www.efmr.org (717)541-1101 Fax (717) 541-5487 Coordinator: Eric Epstein Authors: Diane Little Janna Match Illustrator: Ezra Match 2 Contents Background Information Introduction .........................................................................4 Energy Resources .. ………………………………………...…4 Nuclear Energy ...............……………………………………..5 The TMI Nuclear Reactors …………………………………....5 Nuclear Waste and Environmental Impacts .........................6 The TMI Unit Two Accident …………………………………..7 Elementary Lesson Plans Activity 1: Introduction to Energy …………………………. ...10 Activity 2: A Chain Reaction …....…………………………....11 Activity 3: Steam Turns Turbines ……………………….…....12 Activity 4: Reviewing Fission and Introducing the TMI Unit Two Accident ………………………….....12 Activity 5: Loss of Coolant in the TMI Unit Two Accident ….14 Activity 6: The Effects of the TMI Accident: Facts and Opinions …………….……...…………...15 Middle School Lesson Plans Activity 1: Comparing Energy Resources …………..……….16 Activity 2: Nuclear Reactor Model Demonstration ….............17 Activity 3: Simulating the TMI-2 Accident …………………….19 Activity 4: The Effects of the Accident ……………….….……20 Activity 5: Comparing the TMI-2 Accident to the