Tools for the Automatic Design of Nuclear Reactor Core Configurations for Fuel Reload, (Re)Arranging New and Partly Spent Fuel
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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). -
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). -
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 -
Fact Sheet on U.S. Nuclear Powered Warship (NPW) Safety
Fact Sheet on U.S. Nuclear Powered Warship (NPW) Safety 1. Commitments of the U.S. Government about the Safety of U.S. NPWs U.S. Nuclear Powered Warships (NPWs) have safely operated for more than 50 years without experiencing any reactor accident or any release of radioactivity that hurt human health or had an adverse effect on marine life. Naval reactors have an outstanding record of over 134 million miles safely steamed on nuclear power, and they have amassed over 5700 reactor-years of safe operation. Currently, the U.S. has 83 nuclear-powered ships: 72 submarines, 10 aircraft carriers and one research vessel. These NPWs make up about forty percent of major U.S. naval combatants, and they visit over 150 ports in over 50 countries, including approximately 70 ports in the U.S. and three in Japan. Regarding the safety of NPWs visiting Japanese ports, the U.S. Government has made firm commitments including those in the Aide-Memoire of 1964; the Statement by the U.S. Government on Operation of Nuclear Powered Warships in Foreign Ports of 1964; the Aide-Memoire of 1967; and the Memorandum of Conversation of 1968. Since 1964 U.S. NPWs have visited Japanese ports (i.e., Yokosuka, Sasebo and White Beach) more than 1200 times. The results of monitoring in these ports conducted by the Government of Japan and the U.S. Government, respectively, demonstrate that the operation of U.S. NPWs does not result in any increase in the general background radioactivity of the environment. The U.S. Government states that every single aspect of these commitments continues to be firmly in place. -
Medline-Sourced Journals Are Indicated in Green) Print-ISSN E-ISSN
Sourcerecord id Source Title (Medline-sourced journals are indicated in Green) Print-ISSN E-ISSN 18500162600 21st Century Music 15343219 21100404576 2D Materials 20531583 21100447128 3 Biotech 2190572X 21905738 21100779062 3D Printing and Additive Manufacturing 23297662 23297670 21100229836 3D Research 20926731 19700200922 3L: Language, Linguistics, Literature 01285157 145295 4OR 16194500 16142411 16400154734 A + U-Architecture and Urbanism 03899160 5700161051 A Contrario 16607880 21100399164 A&A case reports 23257237 21100881366 A&A practice 25753126 19600162043 A.M.A. American Journal of Diseases of Children 00968994 19400157806 A.M.A. archives of dermatology 00965359 19600162081 A.M.A. Archives of Dermatology and Syphilology 00965979 19400157807 A.M.A. archives of industrial health 05673933 19600162082 A.M.A. Archives of Industrial Hygiene and Occupational Medicine 00966703 19400157808 A.M.A. archives of internal medicine 08882479 19400158171 A.M.A. archives of neurology 03758540 19400157809 A.M.A. archives of neurology and psychiatry 00966886 19400157810 A.M.A. archives of ophthalmology 00966339 19400157811 A.M.A. archives of otolaryngology 00966894 19400157812 A.M.A. archives of pathology 00966711 19400157813 A.M.A. archives of surgery 00966908 21100456161 a/b: Auto/Biography Studies 21517290 11600153683 A|Z ITU Journal of Faculty of Architecture 13028324 21100780699 A+BE Architecture and the Built Environment 22123202 22147233 5800207606 AAA, Arbeiten aus Anglistik und Amerikanistik 01715410 28033 AAC: Augmentative and Alternative -
Research Reactor Core Conversion Guidebook
IAEA-TECDOC-643 Research reactor core conversion guidebook Volume 5: Operations (Appendices L-N) INTERNATIONAL ATOMIC ENERGY AGENCY /A> RESEARCH REACTOR CORE CONVERSION GUIDEBOOK VOLUME 5: OPERATIONS (APPENDICES L-N) IAEA, VIENNA, 1992 IAEA-TECDOC-643 ISSN 1011-4289 Printed by the IAEA in Austria April 1992 FOREWORD In view of the proliferation concerns caused by the use of highly enriched uranium (HEU) and in anticipation that the supply of HEU to research and test reactors will be more restricted in the future, this guidebook has been prepared to assist research reactor operators in addressing the safety d licensinan g issue conversior fo s f theino r reactoU HE r f coreo e sus froe th m fuel to the use of low enriched uranium (LEU) fuel. Two previous guidebooks on research reactor core conversion have been publishe e IAEAe th firsTh .y tb d guidebook (IAEA-TECDOC-233) addressed feasibility studies and fuel development potential for light-water-moderated research reactors and the second guidebook (IAEA-TECDOC-324) addressed these topic r heavy-water-moderatefo s d research reactors. This guidebook n fivi , e volumes, addresses the effects of changes in the safety-related parameters of mixed cores and the converted core. It provides an information base which should enable the appropriate approvals processes for implementation of a specific conversion proposal, whether for a light or for a heavy water moderated research reactor greatle b o ,t y facilitated. This guidebook has been prepared at a number of Technical Committee Meetings and Consultants Meetings and coordinated by the Physics Section of the International Atomic Energy Agency, with contributions volunteerey b d different organizations. -
Compare and Contrast Major Nuclear Power Plant Disasters: Lessons Learned from the Past
163 10th International Conference of the International Institute for Infrastructure Resilience and Reconstruction (I3R2) 20–22 May 2014 Purdue University, West Lafayette, Indiana, USA Compare and Contrast Major Nuclear Power Plant Disasters: Lessons Learned from the Past Sayanti Mukhopadhyay and Makarand Hastak Construction Engineering and Management, Purdue University Jessica Halligan School of Nuclear Engineering, Purdue University ABSTRACT The construction of nuclear power plants is a major step towards reducing greenhouse gas emissions compared to the conventional coal-fired or oil-fired power plants. However, some of the major nuclear accidents in the past have raised questions about the safety and reliability of nuclear power plants. This paper compares and contrasts the major nuclear accidents of the past for example, the Chernobyl disaster (USSR), the Fukushima Daiichi disaster (Japan), and the Three Mile Island incident (USA). Although each of the accidents was unique, a thorough comparison found some common issues, such as faulty design of reactors and safety systems, safety rules violations, and lack of trained operators. The primary impacts mostly involved radiation hazards such as exposure to varying doses of radiation, uninhabitable neighborhoods and health problems; the levels of impact varied mostly due to different intensities of warnings and precautionary measures taken by the local governments. The research findings would serve as an important resource for the nuclear professionals to plan proper precautionary measures in order to avoid the major issues that initiated or resulted from the accidents in the past. 1. INTRODUCTION summarizes the important lessons learned from the past instances which could serve as an Nuclear power plants are one of the most complex information tool for the nuclear professionals to and sophisticated energy systems designed to plan for proper preventive measures well in produce low carbon electrical energy in contrast to advance to avoid similar accidents in future. -
Module04 Design of a Nuclear Reactor
Module IV Design of a nuclear reactor International Atomic Energy Agency, May 2015 v1.0 Background In 1991, the General Conference (GC) in its resolution RES/552 requested the Director General to prepare 'a comprehensive proposal for education and training in both radiation protection and in nuclear safety' for consideration by the following GC in 1992. In 1992, the proposal was made by the Secretariat and after considering this proposal the General Conference requested the Director General to prepare a report on a possible programme of activities on education and training in radiological protection and nuclear safety in its resolution RES1584. In response to this request and as a first step, the Secretariat prepared a Standard Syllabus for the Post- graduate Educational Course in Radiation Protection. Subsequently, planning of specialised training courses and workshops in different areas of Standard Syllabus were also made. A similar approach was taken to develop basic professional training in nuclear safety. In January 1997, Programme Performance Assessment System (PPAS) recommended the preparation of a standard syllabus for nuclear safety based on Agency Safely Standard Series Documents and any other internationally accepted practices. A draft Standard Syllabus for Basic Professional Training Course in Nuclear Safety (BPTC) was prepared by a group of consultants in November 1997 and the syllabus was finalised in July 1998 in the second consultants meeting. The Basic Professional Training Course on Nuclear Safety was offered for the first time at the end of 1999, in English, in Saclay, France, in cooperation with Institut National des Sciences et Techniques Nucleaires/Commissariat a l'Energie Atomique (INSTN/CEA). -
Nuclear Reactor Core Model for the Advanced Nuclear Fuel Cycle Simulator FANCSEE
TVE-F 17 009 juni Examensarbete 15 hp Juni 2017 Nuclear reactor core model for the advanced nuclear fuel cycle simulator FANCSEE. Advanced use of Monte Carlo methods in nuclear reactor calculations Alexander Skwarcan-Bidakowski Abstract Nuclear reactor core model for the advanced nuclear fuel cycle simulator FANCSEE. Advanced use of Monte Carlo methods in nuclear reactor calculations Alexander Skwarcan-Bidakowski Teknisk- naturvetenskaplig fakultet UTH-enheten A detailed reactor core modeling of the LOVIISA-2 PWR and FORSMARK-3 BWR was performed in the Serpent 2 Continuous Energy Monte-Carlo Besöksadress: code. Ångströmlaboratoriet Lägerhyddsvägen 1 Hus 4, Plan 0 Both models of the reactors were completed but the approximations of the atomic densities of nuclides present in the core differed Postadress: significantly. Box 536 751 21 Uppsala In the LOVIISA-2 PWR, the predicted atomic density for the nuclides Telefon: approximated by Chebyshev Rational Approximation method (CRAM) 018 – 471 30 03 coincided with the corrected atomic density simulated by the Serpent Telefax: 2 program. In the case of FORSMARK-3 BWR, the atomic density from 018 – 471 30 00 CRAM poorly approximated the data returned by the simulation in Serpent 2. Due to boiling of the moderator in the core of FORSMARK-3, Hemsida: the model seemed to encounter problems of fission density, which http://www.teknat.uu.se/student yielded unusable results. The results based on the models of the reactor cores are significant to the FANCSEE Nuclear fuel cycle simulator, which will be used as a dataset for the nuclear fuel cycle burnup in the reactors. Handledare: prof. -
Nuclear Energy of the Future: What Research for Which Objectives?
MonoCEA GB 5/04/06 15:30 Page 3 Commissariat à l’énergie atomique e-den A monograph of the Nuclear Energy Directorate Nuclear energy of the future: what research for which objectives? Éditions techniques MonoCEA GB 5/04/06 15:30 Page 2 DEN monographs A monograph of the Nuclear Energy Directorate Commissariat à l’énergie atomique, 31-33, rue de la Fédération 75752 Paris Cedex 15 Tél. : +33-1 40 56 10 00 Scientific comitee Michel Alexandre, Michel Beauvy, Georges Berthoud, Mireille Defranceschi, Gérard Ducros, Yannick Guérin, Yves Limoge, Charles Madic, Gérard Santarini, Jean-Marie Seiler, Pierre Sollogoub, Étienne Vernaz, Research Directors. The following people participated in this work: Fanny Bazile, Patrice Bernard, Bernard Bonin, Jacques Bouchard, Jean-Claude Bouchter, Bernard Boullis, Franck Carré, Jean Cazalet, Alain Marvy, Valérie Moulin, Emmanuel Touron, Yves Terrien. Publishing Supervisor: Philippe Pradel. Editorial Board: Bernard Bonin (Managing Editor), Bernard Bouquin, Martine Dozol, Michel Jorda, Jean-Pierre Moncouyoux, Alain Vallée. Administrator: Fanny Bazile. Editor: Jean-François Parisot. Graphic concept: Pierre Finot. Cover illustration: Véronique Frouard. Correspondence: all correspondence can be addressed to the Editor or to CEA / DEN Direction scientifique, CEA Saclay 91191 Gif-sur-Yvette Cedex. Tél. : + 33-1 69 08 16 75. © CEA Saclay and Groupe Moniteur (Éditions du Moniteur), Paris, 2006 The information contained in this document can be freely reproduced, with the agreement of the Editorial Board and due mention of its origin. MonoCEA GB 5/04/06 15:30 Page 5 Preface After a dazzling start in the 1950s as a promising, inexhaustible, cost-effective energy source, nuclear energy was rejected by majority opinion in several countries in North America and Western Europe three to four decades later, suddenly bringing its development to a halt. -
2018 Journal Citation Reports Journals in the 2018 Release of JCR 2 Journals in the 2018 Release of JCR
2018 Journal Citation Reports Journals in the 2018 release of JCR 2 Journals in the 2018 release of JCR Abbreviated Title Full Title Country/Region SCIE SSCI 2D MATER 2D MATERIALS England ✓ 3 BIOTECH 3 BIOTECH Germany ✓ 3D PRINT ADDIT MANUF 3D PRINTING AND ADDITIVE MANUFACTURING United States ✓ 4OR-A QUARTERLY JOURNAL OF 4OR-Q J OPER RES OPERATIONS RESEARCH Germany ✓ AAPG BULL AAPG BULLETIN United States ✓ AAPS J AAPS JOURNAL United States ✓ AAPS PHARMSCITECH AAPS PHARMSCITECH United States ✓ AATCC J RES AATCC JOURNAL OF RESEARCH United States ✓ AATCC REV AATCC REVIEW United States ✓ ABACUS-A JOURNAL OF ACCOUNTING ABACUS FINANCE AND BUSINESS STUDIES Australia ✓ ABDOM IMAGING ABDOMINAL IMAGING United States ✓ ABDOM RADIOL ABDOMINAL RADIOLOGY United States ✓ ABHANDLUNGEN AUS DEM MATHEMATISCHEN ABH MATH SEM HAMBURG SEMINAR DER UNIVERSITAT HAMBURG Germany ✓ ACADEMIA-REVISTA LATINOAMERICANA ACAD-REV LATINOAM AD DE ADMINISTRACION Colombia ✓ ACAD EMERG MED ACADEMIC EMERGENCY MEDICINE United States ✓ ACAD MED ACADEMIC MEDICINE United States ✓ ACAD PEDIATR ACADEMIC PEDIATRICS United States ✓ ACAD PSYCHIATR ACADEMIC PSYCHIATRY United States ✓ ACAD RADIOL ACADEMIC RADIOLOGY United States ✓ ACAD MANAG ANN ACADEMY OF MANAGEMENT ANNALS United States ✓ ACAD MANAGE J ACADEMY OF MANAGEMENT JOURNAL United States ✓ ACAD MANAG LEARN EDU ACADEMY OF MANAGEMENT LEARNING & EDUCATION United States ✓ ACAD MANAGE PERSPECT ACADEMY OF MANAGEMENT PERSPECTIVES United States ✓ ACAD MANAGE REV ACADEMY OF MANAGEMENT REVIEW United States ✓ ACAROLOGIA ACAROLOGIA France ✓