Nuclear Reactor Realities
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Compilation and Evaluation of Fission Yield Nuclear Data Iaea, Vienna, 2000 Iaea-Tecdoc-1168 Issn 1011–4289
IAEA-TECDOC-1168 Compilation and evaluation of fission yield nuclear data Final report of a co-ordinated research project 1991–1996 December 2000 The originating Section of this publication in the IAEA was: Nuclear Data Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria COMPILATION AND EVALUATION OF FISSION YIELD NUCLEAR DATA IAEA, VIENNA, 2000 IAEA-TECDOC-1168 ISSN 1011–4289 © IAEA, 2000 Printed by the IAEA in Austria December 2000 FOREWORD Fission product yields are required at several stages of the nuclear fuel cycle and are therefore included in all large international data files for reactor calculations and related applications. Such files are maintained and disseminated by the Nuclear Data Section of the IAEA as a member of an international data centres network. Users of these data are from the fields of reactor design and operation, waste management and nuclear materials safeguards, all of which are essential parts of the IAEA programme. In the 1980s, the number of measured fission yields increased so drastically that the manpower available for evaluating them to meet specific user needs was insufficient. To cope with this task, it was concluded in several meetings on fission product nuclear data, some of them convened by the IAEA, that international co-operation was required, and an IAEA co-ordinated research project (CRP) was recommended. This recommendation was endorsed by the International Nuclear Data Committee, an advisory body for the nuclear data programme of the IAEA. As a consequence, the CRP on the Compilation and Evaluation of Fission Yield Nuclear Data was initiated in 1991, after its scope, objectives and tasks had been defined by a preparatory meeting. -
Modelling Transport and Deposition of Caesium and Iodine from the Chernobyl Accident Using the DREAM Model J
Modelling transport and deposition of caesium and iodine from the Chernobyl accident using the DREAM model J. Brandt, J. H. Christensen, L. M. Frohn To cite this version: J. Brandt, J. H. Christensen, L. M. Frohn. Modelling transport and deposition of caesium and iodine from the Chernobyl accident using the DREAM model. Atmospheric Chemistry and Physics, European Geosciences Union, 2002, 2 (5), pp.397-417. hal-00295217 HAL Id: hal-00295217 https://hal.archives-ouvertes.fr/hal-00295217 Submitted on 17 Dec 2002 HAL is a multi-disciplinary open access L’archive ouverte pluridisciplinaire HAL, est archive for the deposit and dissemination of sci- destinée au dépôt et à la diffusion de documents entific research documents, whether they are pub- scientifiques de niveau recherche, publiés ou non, lished or not. The documents may come from émanant des établissements d’enseignement et de teaching and research institutions in France or recherche français ou étrangers, des laboratoires abroad, or from public or private research centers. publics ou privés. Atmos. Chem. Phys., 2, 397–417, 2002 www.atmos-chem-phys.org/acp/2/397/ Atmospheric Chemistry and Physics Modelling transport and deposition of caesium and iodine from the Chernobyl accident using the DREAM model J. Brandt, J. H. Christensen, and L. M. Frohn National Environmental Research Institute, Department of Atmospheric Environment, Frederiksborgvej 399, P.O. Box 358, DK-4000 Roskilde, Denmark Received: 11 April 2002 – Published in Atmos. Chem. Phys. Discuss.: 24 June 2002 Revised: 9 September 2002 – Accepted: 24 September 2002 – Published: 17 December 2002 Abstract. A tracer model, DREAM (the Danish Rimpuff and low cloud scavenging process for the submicron particles and Eulerian Accidental release Model), has been developed for that the precipitation rates are relatively uncertain in the me- modelling transport, dispersion and deposition (wet and dry) teorological model compared to the relative humidity. -
New York State Department of Health Environmental Radiation Program Environmental Radiation Surveillance Site Readings
New York State Department of Health Environmental Radiation Program Environmental Radiation Surveillance Site Readings Glossary This glossary has been added in order to define technical terms that are used in the various supporting documents for this data set. Please refer to the Data Dictionary for explanation of the meaning of the column headings in the data set. 1. Alpha particles- a positively charged particle made up of two neutrons and two protons emitted by certain radioactive nuclei. a. Gross alpha radioactivity- a measurement of all alpha activity present, regardless of specific radionuclide source. 2. Americium (chemical symbol Am) - is a man-made radioactive metal, with Atomic Number 95. The most important isotope of Americium is Am-241. 3. Background radiation- is radiation that results from natural sources such as cosmic radiation and naturally-occurring radioactive materials in the ground and the earth’s atmosphere including radon. 4. Beta particles- an electron or positron emitted by certain radioactive nuclei. Beta particles can be stopped by aluminum. a. Gross beta radioactivity- measurement of all beta activity present, regardless of specific radionuclide source. 5. Cerium (chemical symbol Ce) - an iron-gray, lustrous metal. Cerium-141, -143, and - 144 are radioisotopes of cerium. 6. Cesium (chemical symbol Cs) - is a metal that may be stable (nonradioactive) or unstable (radioactive). The most common radioactive form of cesium is cesium-137. Another fairly common radioisotope is cesium-134. 7. Cobalt (chemical symbol Co) - is a metal that may be stable (non-radioactive, as found in nature), or unstable (radioactive, man-made). The most common radioactive isotope of cobalt is cobalt-60. -
12 Natural Isotopes of Elements Other Than H, C, O
12 NATURAL ISOTOPES OF ELEMENTS OTHER THAN H, C, O In this chapter we are dealing with the less common applications of natural isotopes. Our discussions will be restricted to their origin and isotopic abundances and the main characteristics. Only brief indications are given about possible applications. More details are presented in the other volumes of this series. A few isotopes are mentioned only briefly, as they are of little relevance to water studies. Based on their half-life, the isotopes concerned can be subdivided: 1) stable isotopes of some elements (He, Li, B, N, S, Cl), of which the abundance variations point to certain geochemical and hydrogeological processes, and which can be applied as tracers in the hydrological systems, 2) radioactive isotopes with half-lives exceeding the age of the universe (232Th, 235U, 238U), 3) radioactive isotopes with shorter half-lives, mainly daughter nuclides of the previous catagory of isotopes, 4) radioactive isotopes with shorter half-lives that are of cosmogenic origin, i.e. that are being produced in the atmosphere by interactions of cosmic radiation particles with atmospheric molecules (7Be, 10Be, 26Al, 32Si, 36Cl, 36Ar, 39Ar, 81Kr, 85Kr, 129I) (Lal and Peters, 1967). The isotopes can also be distinguished by their chemical characteristics: 1) the isotopes of noble gases (He, Ar, Kr) play an important role, because of their solubility in water and because of their chemically inert and thus conservative character. Table 12.1 gives the solubility values in water (data from Benson and Krause, 1976); the table also contains the atmospheric concentrations (Andrews, 1992: error in his Eq.4, where Ti/(T1) should read (Ti/T)1); 2) another category consists of the isotopes of elements that are only slightly soluble and have very low concentrations in water under moderate conditions (Be, Al). -
Correspondence Continuing Education for Nuclear Pharmacists
THE UNIVERSITY OF NEW MEXICO COLLEGE OF PHARMACY ALBUQUERQUE, NEW MEXICO The University of New Mexico Correspondence Continuing Education Courses for Nuclear Pharmacists and Nuclear Medicine Professionals VOLUME II, NUMBER 1 Radionuclide Therapy of Painful Osseous Metastasis by: Jay A. Spicer, M.S. Co-sponsored by: mpi pharmc~ services inc an mersham company The University of New Mexico College of Phamcy is approved by the American Council on Pharmaceutical Education as a provider of continuing pharmaceutical education. Program No. 180-039-93-M6. 2.5 Contact Hours or ,25 CEU’S H m Edtior William B. Hladik III, M. S., R.Ph., University of New Mexico Director of Pharmacy Continuing Education Hugh F. Kabat, Ph. D., University of New Mexico While the advice and information in this publication are believed to be true and accurate at press time, neither the author(s) nor the editor nor the publisher ean accept any legal responsibility for any errors or omissions that may be made. The publisher makes no warranty, express or implid, with res~t to the matetial contained herein. The UNMPharmacy Contittutiig Educatwn Stifl and the Edtior WOUUlike to gratefully achnowkdge Sharon I, Ramirez for her technical suppoti and assktince in the producttin of this pubtiation. Copyright 1993 University of New Mexico Pharmacy Continuing Education Albuquerque, New Mexico HIONUCLIDE THERAPY OF PAINFUL OSSEOUS METASTASIS STATEMENT OF OBJECTIVES This correspondence course is intended to increase tie reader’s knowledge of radiophmaceuticals that are used in the treatment of pain associated with bone metastasis from different types of cancer. A variety of aspects regarding the agents currently being usti or tested are discussed. -
Global Fissile Material Report 2006 a Table of Contents
IPF M Global Fis sile Material Report Developing the technical basis for policy initiatives to secure and irreversibly reduce stocks of nuclear weapons and fissile materials 2006 Over the past six decades, our understanding of the nuclear danger has expanded from the threat posed by the vast nuclear arsenals created by the super- powers in the Cold War to encompass the prolifera- tion of nuclear weapons to additional states and now also to terrorist groups. To reduce this danger, it is essential to secure and to sharply reduce all stocks of highly enriched uranium and separated plutonium, the key materials in nuclear weapons, and to limit any further production. The mission of the IPFM is to advance the technical basis for cooperative international policy initiatives to achieve these goals. A report published by Global Fissile The International Panel on Fissile Materials (IPFM) www.fissilematerials.org Program on Science and Global Security Princeton University Material Report 2006 221 Nassau Street, 2nd Floor Princeton, NJ 08542, USA First report of the International Panel on Fissile Materials First report of the International Panel on Fissile Materials Developing the Technical Basis for Policy Initiatives to Secure and Irreversibly Reduce Stocks of Nuclear Weapons and Fissile Materials www.fissilematerials.org Global Fissile Material Report 2006 a Table of Contents About the IPFM 1 Summary 2 I. Background 5 1 Fissile Materials and Nuclear Weapons 6 2 Nuclear-Weapon and Fissile-Material Stocks 12 3 Production and Disposition of Fissile -
Implications of the Accident at Chernobyl for Safety Regulation of Commercial Nuclear Power Plants in the United States Final Report
NUREG-1251 Vol. I Implications of the Accident at Chernobyl for Safety Regulation of Commercial Nuclear Power Plants in the United States Final Report Main Report U.S. Nuclear Regulatory Commission p. o 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 2. The Superintendent of Documents, U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20013-7082 3. The National Technical Information Service, Springfield, VA 22161 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 Office of Inspection and Enforcement bulletins, circulars, information notices, inspection and investi- gation notices; Licensee Event Reports; vendor reports and correspondence; Commission papers; and applicant and licensee documents and correspondence. The following documents in the NUREG series are available for purchase from the GPO Sales Program: formal NRC staff and contractor reports, NRC-sponsored conference proceed- ings, and NRC booklets and brochures. Also available are Regulatory Guides, NRC regula- tions in the Code of Federal Regulations, 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. -
Redalyc.Axial Neutron Flux Evaluation in a Tokamak System: a Possible Transmutation Blanket Position for a Fusion-Fission Transm
Brazilian Journal of Physics ISSN: 0103-9733 [email protected] Sociedade Brasileira de Física Brasil Velasquez, Carlos E.; Barros, Graiciany de P.; Pereira, Claubia; Fortini Veloso, Maria A.; Costa, Antonella L. Axial Neutron Flux Evaluation in a Tokamak System: a Possible Transmutation Blanket Position for a Fusion-Fission Transmutation System Brazilian Journal of Physics, vol. 42, núm. 3-4, julio-diciembre, 2012, pp. 237-247 Sociedade Brasileira de Física Sâo Paulo, Brasil Available in: http://www.redalyc.org/articulo.oa?id=46423465009 How to cite Complete issue Scientific Information System More information about this article Network of Scientific Journals from Latin America, the Caribbean, Spain and Portugal Journal's homepage in redalyc.org Non-profit academic project, developed under the open access initiative Braz J Phys (2012) 42:237–247 DOI 10.1007/s13538-012-0081-2 NUCLEAR PHYSICS Axial Neutron Flux Evaluation in a Tokamak System: a Possible Transmutation Blanket Position for a Fusion–Fission Transmutation System Carlos E. Velasquez & Graiciany de P. Barros & Claubia Pereira & Maria A. Fortini Veloso & Antonella L. Costa Received: 28 August 2011 /Published online: 17 May 2012 # Sociedade Brasileira de Física 2012 Abstract A sub-critical advanced reactor based on Tokamak regions more suitable to transmutation were determined. The technology with a D–T fusion neutron source is an innovative results demonstrated that the best zone in which to place a type of nuclear system. Due to the large number of neutrons transmutation blanket is limited by the heat sink and the shield produced by fusion reactions, such a system could be useful in block. -
Fundamentals of Nuclear Reactor Physics
Fundamentals of Nuclear Reactor Physics E. E. Lewis Professor of Mechanical Engineering McCormick School of Engineering and Applied Science Northwestern University AMSTERDAM • BOSTON • HEIDELBERG • LONDON NEW YORK • OXFORD • PARIS • SAN DIEGO SAN FRANCISCO • SINGAPORE • SYDNEY • TOKYO ELSEVIER Academie Press is an imprint of Elsevier Contents Preface xiii 1 Nuclear Reactions 1 1.1 Introduction 1 1.2 Nuclear Reaction Fundamentals 2 Reaction Equations 3 Notation 5 Energetics 5 1.3 The Curve of Binding Energy 7 1.4 Fusion Reactions 8 1.5 Fission Reactions 9 Energy Release and Dissipation 10 Neutron Multiplication 12 Fission Products 13 1.6 Fissile and Fertile Materials 16 1.7 Radioactive Decay 18 Saturation Activity 20 Decay Chains 21 2 Neutron Interactions 29 2.1 Introduction 29 2.2 Neutron Cross Sections 29 Microscopic and Macroscopic Cross Sections 30 Uncollided Flux 32 Nuclide Densities 33 Enriched Uranium 35 Cross Section Calculation Example 36 Reaction Types 36 2.3 Neutron Energy Range 38 2.4 Cross Section Energy Dependence 40 Compound Nucleus Formation 41 Resonance Cross Sections 42 Threshold Cross Sections 46 Fissionable Materials 47 vii viii Contents 2.5 Neutron Scattering 48 Elastic Scattering 49 Slowing Down Decrement 50 Inelastic Scattering 52 3 Neutron Distributions in Energy 57 3.1 Introduction 57 3.2 Nuclear Fuel Properties 58 3.3 Neutron Moderators 61 3.4 Neutron Energy Spectra 63 Fast Neutrons 65 Neutron Slowing Down 66 Thermal Neutrons 70 Fast and Thermal Reactor Spectra 72 3.5 -
Calculating Nuclear Accident Probabilities from Empirical Frequencies Minh Ha-Duong, V
Calculating nuclear accident probabilities from empirical frequencies Minh Ha-Duong, V. Journé To cite this version: Minh Ha-Duong, V. Journé. Calculating nuclear accident probabilities from empirical frequencies. Environment Systems and Decisions, Springer, 2014, 34 (2), pp.249-258. 10.1007/s10669-014-9499-0. hal-01018478v2 HAL Id: hal-01018478 https://hal.archives-ouvertes.fr/hal-01018478v2 Submitted on 21 Jul 2014 HAL is a multi-disciplinary open access L’archive ouverte pluridisciplinaire HAL, est archive for the deposit and dissemination of sci- destinée au dépôt et à la diffusion de documents entific research documents, whether they are pub- scientifiques de niveau recherche, publiés ou non, lished or not. The documents may come from émanant des établissements d’enseignement et de teaching and research institutions in France or recherche français ou étrangers, des laboratoires abroad, or from public or private research centers. publics ou privés. Distributed under a Creative Commons Attribution - NonCommercial - ShareAlike| 4.0 International License Manuscript to appear in Environment, Systems and Decisions CALCULATING NUCLEAR ACCIDENT PROBABILITIES FROM EMPIRICAL FREQUENCIES Minh Ha-Duong et Venance Journé1 2014-04-10 Summary Since there is no authoritative, comprehensive and public historical record of nuclear power plant accidents, we reconstructed a nuclear accident dataset from peer-reviewed and other literature. We found that, in a sample of five random years, the worldwide historical frequency of a nuclear major accident, defined as an INES level 7 event, is 14%. This value is 67 % to have at least one nuclear accident rated at level ≥ 4 on the INES scale. These numbers are subject to uncertainties because the fuzziness of the definition of a nuclear accident. -
The SL-1 Accident Consequences
The SL-1 Accident Consequences Key Things to Remember On the night of January 3, 1961, the SL-1 nuclear reactor, a About prototype for a military installation to be used in remote Arctic SL-1 Accident Consequences: locations, exploded, killing the three-member military crew. The crew had been performing the routine process of re-assembling 1. The SL-1’s highly enriched fuel the reactor control rod drive mechanisms during a reactor outage. had high burnup and had The SL-1 was a small 3 Mega-Watt-thermal (MWt) boiling water operated for 932 MW-days, reactor, complete with a turbine-generator and condenser building up fission products in designed to generate both electric power and building heat. 1 the fuel before the accident. 2. The SL-1 condensers were on The SL-1 was designed, constructed and initially operated by the top of the building and the Argonne National Laboratory. It was located at the Idaho reactor was in a ventilated National Laboratory, then called the National Reactor Testing building with no containment. Station. Combustion Engineering became the operating 3. About 30 percent of SL-1’s fuel contractor for the Atomic Energy Commission (now the was absent from the reactor Department of Energy) for SL-1 on February 5, 1959. vessel after the accident. 4. The AEC claimed that basically The SL-1 had first gone critical on August 1, 1958 and by only iodine-131 was in the July 1, 1959 had accumulated 160 Mega-Watt operating days radioactive plume from the (MWD). By August 21, 1960, the reactor had accumulated 680 accident. -
Module01 Nuclear Physics and Reactor Theory
Module I Nuclear physics and reactor theory 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).