Compare and Contrast Major Nuclear Power Plant Disasters: Lessons Learned from the Past
Total Page:16
File Type:pdf, Size:1020Kb
Load more
Recommended publications
-
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). -
Significant Incidents in Nuclear Fuel Cycle Facilities
IAEA-TECDOC-867 Significant incidents in nuclear fuel cycle INTERNATIONAL ATOMIC ENERGY AGENCY The IAEA does not normally maintain stocks of reports in this series. However, microfiche copie f thesso e reportobtainee b n sca d from INIS Clearinghouse International Atomic Energy Agency Wagramerstrasse 5 P.O. Box 100 A-1400 Vienna, Austria Orders should be accompanied by prepayment of Austrian Schillings 100, in the form of a cheque or in the form of IAEA microfiche service coupons which may be ordered separately from the INIS Clearinghouse. The originating Section of this publication in the IAEA was: Nuclear Fuel Cycle and Materials Section International Atomic Energy aoiicy A Wagramerstrasse 5 0 10 P.Ox Bo . A-1400 Vienna, Austria SIGNIFICANT INCIDENT NUCLEASN I R FUEL CYCLE FACILITIES IAEA, VIENNA, 1996 IAEA-TECDOC-867 ISSN 1011-4289 ©IAEA, 1996 Printe IAEe th AustriAn y i d b a March 1996 FOREWORD significano Tw t accidents have occurre histore th n di f nuclea yo r power, namely t Threa , e Mile Islan Chernobyld dan orden I . preveno rt t such accidents, causes were investigate actiond dan s were taken r exampleFo . , reporting systems were establishe accumulato dt disseminatd ean e information on accidents such as INES (International Nuclear Event Scale) and IRS (Incident Reporting System). Operators of nuclear power plants also established an information system to share incident information. The purpose of INES is to facilitate prompt communication between the nuclear community, the media and the public. The purpose of IRS is to analyse causes of significant incidents. Those systems serve to promote safety culture in nuclear power plants. -
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. -
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. -
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). -
The Nuclear Accident at Chernobyl: Immediate and Further Consequences
The article was received on September 10, 2020, and accepted for publishing on February 13, 2021. VARIA The nuclear accident at Chernobyl: Immediate and further consequences Symeon Naoum1, Vasileios Spyropoulos1 Abstract: The accident at Chernobyl occurred in April 1986 at the Chernobyl Nuclear Power Plant in Soviet Union. The incident occurred during a scheduled safety test. A combination of inherent reactor design flaws and operators’ mistakes resulted in reactor’s No.4 disaster and the emission of a large quantity of radiation. The immediate actions involved the fire extinguishing, the cleanup of radioactive residues and the prevention of a new explosion. For this purpose, plenty of people worked with self-sacrifice. The people who lived nearby were removed. As far as the socio-economic impact for the Soviet Union is concerned, it was quite serious. Moreover, the environmental and human health consequences were also alarming with thyroid cancer being the most studied. Useful conclusions, especially for the safety both of reactors and nuclear power, as well as for the impact of radiation at ecosystems have been drawn. The debate about the use of nuclear power has remained open ever since. Keywords: nuclear power, thyroid cancer, RBMK reactor, radiation, radioactivity, liquidators INTRODUCTION while 28 firemen and employees finally died. The Chernobyl The Chernobyl nuclear accident occurred on 26 April 1986 in accident is considered the most damaging nuclear power the light water graphite moderated reactor No 4 at the plant accident in history. The Chernobyl and the Fukushima Chernobyl Nuclear Power Plant, close the town of Pripyat, in accident are the two nuclear accidents classified as a level 7 Ukrainian Soviet Socialist Republic Soviet Union, roughly (the maximum classification) on the International Nuclear 100km of the city of Kiev [1]. -
The Growth of Nuclear Power: a Detailed Investigation
Journal of Basic and Applied Engineering Research p-ISSN: 2350-0077; e-ISSN: 2350-0255; Volume 2, Number 18; July-September, 2015, pp. 1590-1594 © Krishi Sanskriti Publications http://www.krishisanskriti.org/Publication.html The Growth of Nuclear Power: A Detailed Investigation Soumyajit Saha1, Pallab Ghosh2, Sayantan Mukherjee3, Ayan Mitra4, Diposmit Ghosh5 13rd Year BTech, Civil Engineering Undergraduate Student, University Of Engineering And Management, Jaipur, India 2,3,4,5 3rd Year BTech, Mechanical Engineering Undergraduate Student, University Of Engineering And Management, Jaipur, India Abstract—The concept of atom has existed for many centuries, Nuclear Science because of his contribution to the theory of however the enormous potential of the tiny mass has been realised atomic structure. recently. Atom have a large amount of energy which is required to hold the nuclei together. Certain isotopes of some element can be Albert Einstein developed his theory of the relationship split up and in turn they will release a part of the energy as heat. This between mass and energy one year later. The mathematical entire process is referred to as fission. The heat released in this formula referred to as E=mc2 or energy equal mass times the process can be easily used to generate electricity in power plants. speed of light squared. It took almost 35 year for someone to Uranium -235 (U-235) is one of the isotopes that can be fissioned prove Einstein’s theory. very easily. During fission, U-235 atoms absorb loose neutrons and it becomes unstable and split into light atoms called fission products. The combined mass of the fission products is less than original U- 235. -
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. -
Investigation on Conversion of I-Graphite from Decommissioning of Chernobyl Npp Into a Stable Waste Form Acceptable for Long Term Storage and Disposal
INVESTIGATION ON CONVERSION OF I-GRAPHITE FROM DECOMMISSIONING OF CHERNOBYL NPP INTO A STABLE WASTE FORM ACCEPTABLE FOR LONG TERM STORAGE AND DISPOSAL BORYS ZLOBENKO, YRIY FEDORENKO, VICTOR YATZENKO, BORYS SHABALIN, VADIM SKRIPKIN National Academy of Sciences of Ukraine: State Institution “Institute of Environmental Geochemistry” Department of Nuclear Geochemistry (Radiocarbon Laboratory), Kyiv, Ukraine INTRODUCTION For Ukraine, the main radiocarbon (14C) source is irradiated graphite from Chernobyl Nuclear Power Plant. The ChNPP is a decommissioned nuclear power station about 14 km northwest of the city of Chernobyl, and 110 km north of Kyiv. The ChNPP had four RBMK reactor units. The commissioning of the first reactor in 1977 was followed by reactor No. 2 (1978), No. 3 (1981), and No.4 (1983). Reactors No.3 and 4 were second generation units, whereas Nos.1 and 2 were first-generation units. RBMK is an acronym for "High Power Channel-type Reactor" of a class of graphite-moderated nuclear power reactor with individual fuel channels that uses ordinary water as its coolant and graphite as its moderator. The combination of graphite moderator and water coolant is found in no other type of nuclear reactor. Parameters RBMK-1000 Thermal power, MW 3840 Core diameter, m 11.80 Core height, m 7.0 Core volume, m 765 Mean specific power 5.02 per core volume, MW/m Mean specific power 20.8 per fuel quantity, MW/t Mean power per fuel 18.3 rod length, kW/m On September 9, 1982, a partial core meltdown occurred in Reactor No. 1 at the Chernobyl plant. The extent of the accident was not made public until several years later.