Overview of Tritium Fast-Fission Yields
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Table 2.Iii.1. Fissionable Isotopes1
FISSIONABLE ISOTOPES Charles P. Blair Last revised: 2012 “While several isotopes are theoretically fissionable, RANNSAD defines fissionable isotopes as either uranium-233 or 235; plutonium 238, 239, 240, 241, or 242, or Americium-241. See, Ackerman, Asal, Bale, Blair and Rethemeyer, Anatomizing Radiological and Nuclear Non-State Adversaries: Identifying the Adversary, p. 99-101, footnote #10, TABLE 2.III.1. FISSIONABLE ISOTOPES1 Isotope Availability Possible Fission Bare Critical Weapon-types mass2 Uranium-233 MEDIUM: DOE reportedly stores Gun-type or implosion-type 15 kg more than one metric ton of U- 233.3 Uranium-235 HIGH: As of 2007, 1700 metric Gun-type or implosion-type 50 kg tons of HEU existed globally, in both civilian and military stocks.4 Plutonium- HIGH: A separated global stock of Implosion 10 kg 238 plutonium, both civilian and military, of over 500 tons.5 Implosion 10 kg Plutonium- Produced in military and civilian 239 reactor fuels. Typically, reactor Plutonium- grade plutonium (RGP) consists Implosion 40 kg 240 of roughly 60 percent plutonium- Plutonium- 239, 25 percent plutonium-240, Implosion 10-13 kg nine percent plutonium-241, five 241 percent plutonium-242 and one Plutonium- percent plutonium-2386 (these Implosion 89 -100 kg 242 percentages are influenced by how long the fuel is irradiated in the reactor).7 1 This table is drawn, in part, from Charles P. Blair, “Jihadists and Nuclear Weapons,” in Gary A. Ackerman and Jeremy Tamsett, ed., Jihadists and Weapons of Mass Destruction: A Growing Threat (New York: Taylor and Francis, 2009), pp. 196-197. See also, David Albright N 2 “Bare critical mass” refers to the absence of an initiator or a reflector. -
小型飛翔体/海外 [Format 2] Technical Catalog Category
小型飛翔体/海外 [Format 2] Technical Catalog Category Airborne contamination sensor Title Depth Evaluation of Entrained Products (DEEP) Proposed by Create Technologies Ltd & Costain Group PLC 1.DEEP is a sensor analysis software for analysing contamination. DEEP can distinguish between surface contamination and internal / absorbed contamination. The software measures contamination depth by analysing distortions in the gamma spectrum. The method can be applied to data gathered using any spectrometer. Because DEEP provides a means of discriminating surface contamination from other radiation sources, DEEP can be used to provide an estimate of surface contamination without physical sampling. DEEP is a real-time method which enables the user to generate a large number of rapid contamination assessments- this data is complementary to physical samples, providing a sound basis for extrapolation from point samples. It also helps identify anomalies enabling targeted sampling startegies. DEEP is compatible with small airborne spectrometer/ processor combinations, such as that proposed by the ARM-U project – please refer to the ARM-U proposal for more details of the air vehicle. Figure 1: DEEP system core components are small, light, low power and can be integrated via USB, serial or Ethernet interfaces. 小型飛翔体/海外 Figure 2: DEEP prototype software 2.Past experience (plants in Japan, overseas plant, applications in other industries, etc) Create technologies is a specialist R&D firm with a focus on imaging and sensing in the nuclear industry. Createc has developed and delivered several novel nuclear technologies, including the N-Visage gamma camera system. Costainis a leading UK construction and civil engineering firm with almost 150 years of history. -
Ternary Fission and Quasi-Fission of Superheavy Nuclei and Giant Nuclear Systems
June 17, 2010 18:24 Proceedings Trim Size: 9in x 6in zagrebaev_¯ssion_2010b TERNARY FISSION AND QUASI-FISSION OF SUPERHEAVY NUCLEI AND GIANT NUCLEAR SYSTEMS V.I. ZAGREBAEV, A.V. KARPOV Flerov Laboratory of Nuclear Reactions, JINR, Dubna, Moscow Region, Russia WALTER GREINER Frankfurt Institute for Advanced Studies, J.W. Goethe-UniversitÄat,Germany We found that a true ternary ¯ssion with formation of a heavy third fragment (a new kind of radioactivity) is quite possible for superheavy nuclei due to the strong shell e®ects leading to a three-body clusterization with the two doubly magic tin- like cores. The three-body quasi-¯ssion process could be even more pronounced for giant nuclear systems formed in collisions of heavy actinide nuclei. In this case a three-body clusterization might be proved experimentally by detection of two coincident lead-like fragments in low-energy U+U collisions. 1. Introduction Today the term \ternary ¯ssion" is commonly used to denote the process of formation of light charged particle accompanied ¯ssion 1. This is a rare process (less than 1%) relative to binary ¯ssion, see Fig. 1. As can be seen the probability of such a process decreases sharply with increasing mass number of the accompanied third particle. These light particles are emitted almost perpendicularly with respect to the ¯ssion axis (equatorial emission) 1. It is interpreted as an indication that the light ternary particles are emitted from the neck region and are accelerated by the Coulomb ¯elds of both heavy fragments. In contrast to such a process, the term \true ternary ¯ssion" is used for a simultaneous decay of a heavy nucleus into three fragments of not very di®erent mass 1. -
Re-Examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix
Re-examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix T. E. G. Nicholasa,∗, T. P. Davisb, F. Federicia, J. E. Lelandc, B. S. Patela, C. Vincentd, S. H. Warda a York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD, UK b Department of Materials, University of Oxford, Parks Road, Oxford, OX1 3PH c Department of Electrical Engineering and Electronics, University of Liverpool, Liverpool, L69 3GJ, UK d Centre for Advanced Instrumentation, Department of Physics, Durham University, Durham DH1 3LS, UK Abstract Fusion energy is often regarded as a long-term solution to the world's energy needs. However, even after solving the critical research challenges, engineer- ing and materials science will still impose significant constraints on the char- acteristics of a fusion power plant. Meanwhile, the global energy grid must transition to low-carbon sources by 2050 to prevent the worst effects of climate change. We review three factors affecting fusion's future trajectory: (1) the sig- nificant drop in the price of renewable energy, (2) the intermittency of renewable sources and implications for future energy grids, and (3) the recent proposition of intermediate-level nuclear waste as a product of fusion. Within the scenario assumed by our premises, we find that while there remains a clear motivation to develop fusion power plants, this motivation is likely weakened by the time they become available. We also conclude that most current fusion reactor designs do not take these factors into account and, to increase market penetration, fu- sion research should consider relaxed nuclear waste design criteria, raw material availability constraints and load-following designs with pulsed operation. -
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. -
Wo 2009/108331 A2
(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 3 September 2009 (03.09.2009) WO 2009/108331 A2 (51) International Patent Classification: AO, AT, AU, AZ, BA, BB, BG, BH, BR, BW, BY, BZ, A61K 38/22 (2006.01) CA, CH, CN, CO, CR, CU, CZ, DE, DK, DM, DO, DZ, EC, EE, EG, ES, FI, GB, GD, GE, GH, GM, GT, HN, (21) International Application Number: HR, HU, ID, IL, IN, IS, JP, KE, KG, KM, KN, KP, KR, PCT/US2009/001213 KZ, LA, LC, LK, LR, LS, LT, LU, LY, MA, MD, ME, (22) International Filing Date: MG, MK, MN, MW, MX, MY, MZ, NA, NG, NI, NO, 25 February 2009 (25.02.2009) NZ, OM, PG, PH, PL, PT, RO, RS, RU, SC, SD, SE, SG, SK, SL, SM, ST, SV, SY, TJ, TM, TN, TR, TT, TZ, UA, (25) Filing Language: English UG, US, UZ, VC, VN, ZA, ZM, ZW. (26) Publication Language: English (84) Designated States (unless otherwise indicated, for every (30) Priority Data: kind of regional protection available): ARIPO (BW, GH, 61/066,959 25 February 2008 (25.02.2008) US GM, KE, LS, MW, MZ, NA, SD, SL, SZ, TZ, UG, ZM, Not furnished 25 February 2009 (25.02.2009) US ZW), Eurasian (AM, AZ, BY, KG, KZ, MD, RU, TJ, TM), European (AT, BE, BG, CH, CY, CZ, DE, DK, EE, (71) Applicant and ES, FI, FR, GB, GR, HR, HU, IE, IS, IT, LT, LU, LV, (72) Inventor: FORSLEY, Lawrence, Parker, Galloway MC, MK, MT, NL, NO, PL, PT, RO, SE, SI, SK, TR), [US/US]; 70 Elmwood Avenue, Rochester, NY 1461 1 OAPI (BF, BJ, CF, CG, CI, CM, GA, GN, GQ, GW, ML, (US). -
Relative Fission Product Yield Determination in the Usgs
RELATIVE FISSION PRODUCT YIELD DETERMINATION IN THE USGS TRIGA MARK I REACTOR by Michael A. Koehl © Copyright by Michael A. Koehl, 2016 All Rights Reserved A thesis submitted to the Faculty and the Board of Trustees of the Colorado School of Mines in partial fulfillment of the requirements for the degree of Doctor of Philosophy (Nuclear Engineering). Golden, Colorado Date: ____________________ Signed: ________________________ Michael A. Koehl Signed: ________________________ Dr. Jenifer C. Braley Thesis Advisor Golden, Colorado Date: ____________________ Signed: ________________________ Dr. Mark P. Jensen Professor and Director Nuclear Science and Engineering Program ii ABSTRACT Fission product yield data sets are one of the most important and fundamental compilations of basic information in the nuclear industry. This data has a wide range of applications which include nuclear fuel burnup and nonproliferation safeguards. Relative fission yields constitute a major fraction of the reported yield data and reduce the number of required absolute measurements. Radiochemical separations of fission products reduce interferences, facilitate the measurement of low level radionuclides, and are instrumental in the analysis of low-yielding symmetrical fission products. It is especially useful in the measurement of the valley nuclides and those on the extreme wings of the mass yield curve, including lanthanides, where absolute yields have high errors. This overall project was conducted in three stages: characterization of the neutron flux in irradiation positions within the U.S. Geological Survey TRIGA Mark I Reactor (GSTR), determining the mass attenuation coefficients of precipitates used in radiochemical separations, and measuring the relative fission products in the GSTR. Using the Westcott convention, the Westcott flux, ; modified spectral index, ; neutron temperature, ; and gold-based cadmium ratiosφ were determined for various sampling√⁄ positions in the USGS TRIGA Mark I reactor. -
The Electronuclear Conversion of Fertile to Fissile Material
UCRL-52144 THE ELECTRONUCLEAR CONVERSION OF FERTILE TO FISSILE MATERIAL C. M. Van Atta J. D. Lee H. Heckrotto October 11, 1976 Prepared for U.S. Energy Research & Development Administration under contract No. W-7405-Eng-48 II\M LAWRENCE lUg LIVERMORE k^tf LABORATORY UnrmsilyotCatftxna/lJvofmofe s$ PC DISTRIBUTION OF THIS DOCUMENmmT IS UMUMWTED NOTICE Thii npoit WM prepared w u account of wot* •pomond by UM Uiilttd Stalwi GovcmiMM. Nittim Uw United Stain nor the United Statn Energy tUwardi it Development AdrnWrtrtUon, not «y of thei* employee!, nor any of their contricton, •ubcontrecton, or their employe*!, makti any warranty, expreai « Implied, or muMi any toga) liability oc reeponafctUty for the accuracy, completenni or uMfulntat of uy Information, apperatui, product or proem dlecloead, or repreienl. that tu UM would not *nfrkig» prrrtt*)}MWiwd r%hl». NOTICE Reference to a oompmy or product rum don not imply approval or nconm ndatjon of the product by the Untnrtity of California or the US. Energy Research A Devetopnient Administration to the uchvton of others that may be suitable. Printed In the United Stitei or America Available from National Technical Information Service U.S. Department of Commerce 528S Port Royal Road Springfield, VA 22161 Price: Printed Copy S : Microfiche $2.25 DMimtic P»t» Ranflt PHca *•#» Rtnft MM 001-025 $ 3.50 326-350 10.00 026-050 4.00 351-375 10.50 051-075 4.50 376-400 10.75 076-100 5.00 401-425 11.00 101-125 5.50 426-450 31.75 126-150 6.00 451-475 12.00 151-175 6.75 476-500 12.50 176-200 7.50 501-525 12.75 201-225 7.75 526-550 13.00 526-250 8.00 551-575 13.50 251-275 9.00 576-600 I3.7S 276-300 9.25 601 -up 301-325 9.75 *Ml J2.50 fot «ch iddltlOMl 100 pip tacmitMt from 601 ID 1,000 flfcK IM 54.50 for eicli iMUknal I0O plfe feenmMI om 1,000 p*o. -
Nuclear Energy & the Environmental Debate
FEATURES Nuclear energy & the environmental debate: The context of choices Through international bodies on climate change, the roles of nuclear power and other energy options are being assessed by Evelyne ^Environmental issues are high on international mental Panel on Climate Change (IPCC), which Bertel and Joop agendas. Governments, interest groups, and citi- has been active since 1988. Since the energy Van de Vate zens are increasingly aware of the need to limit sector is responsible for the major share of an- environmental impacts from human activities. In thropogenic greenhouse gas emissions, interna- the energy sector, one focus has been on green- tional organisations having expertise and man- house gas emissions which could lead to global date in the field of energy, such as the IAEA, are climate change. The issue is likely to be a driving actively involved in the activities of these bodies. factor in choices about energy options for elec- In this connection, the IAEA participated in the tricity generation during the coming decades. preparation of the second Scientific Assessment Nuclear power's future will undoubtedly be in- Report (SAR) of the Intergovernmental Panel on fluenced by this debate, and its potential role in Climate Change (IPCC). reducing environmental impacts from the elec- The IAEA has provided the IPCC with docu- tricity sector will be of central importance. mented information and results from its ongoing Scientifically there is little doubt that increas- programmes on the potential role of nuclear ing atmospheric levels of greenhouse gases, such power in alleviating the risk of global climate as carbon dioxide (CO2) and methane, will cause change. -
Inis: Terminology Charts
IAEA-INIS-13A(Rev.0) XA0400071 INIS: TERMINOLOGY CHARTS agree INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, AUGUST 1970 INISs TERMINOLOGY CHARTS TABLE OF CONTENTS FOREWORD ... ......... *.* 1 PREFACE 2 INTRODUCTION ... .... *a ... oo 3 LIST OF SUBJECT FIELDS REPRESENTED BY THE CHARTS ........ 5 GENERAL DESCRIPTOR INDEX ................ 9*999.9o.ooo .... 7 FOREWORD This document is one in a series of publications known as the INIS Reference Series. It is to be used in conjunction with the indexing manual 1) and the thesaurus 2) for the preparation of INIS input by national and regional centrea. The thesaurus and terminology charts in their first edition (Rev.0) were produced as the result of an agreement between the International Atomic Energy Agency (IAEA) and the European Atomic Energy Community (Euratom). Except for minor changesq the terminology and the interrela- tionships btween rms are those of the December 1969 edition of the Euratom Thesaurus 3) In all matters of subject indexing and ontrol, the IAEA followed the recommendations of Euratom for these charts. Credit and responsibility for the present version of these charts must go to Euratom. Suggestions for improvement from all interested parties. particularly those that are contributing to or utilizing the INIS magnetic-tape services are welcomed. These should be addressed to: The Thesaurus Speoialist/INIS Section Division of Scientific and Tohnioal Information International Atomic Energy Agency P.O. Box 590 A-1011 Vienna, Austria International Atomic Energy Agency Division of Sientific and Technical Information INIS Section June 1970 1) IAEA-INIS-12 (INIS: Manual for Indexing) 2) IAEA-INIS-13 (INIS: Thesaurus) 3) EURATOM Thesaurusq, Euratom Nuclear Documentation System. -
Properties of Selected Radioisotopes
CASE FILE COPY NASA SP-7031 Properties of Selected Radioisotopes A Bibliography PART I: UNCLASSIFIED LITERATURE NATIONAL AERONAUTICS AND SPACE ADMINISTRATION NASA SP-7031 PROPERTIES OF SELECTED RADIOISOTOPES A Bibliography Part I: Unclassified Literature A selection of annotated references to technical papers, journal articles, and books This bibliography was compiled and edited by DALE HARRIS and JOSEPH EPSTEIN Goddard Space Flight Center Greenbelt, Maryland Scientific and Technical Information Division / OFFICE OF TECHNOLOGY UTILIZATION 1968 USP. NATIONAL AERONAUTICS AND SPACE ADMINISTRATION Washington, D.C. PREFACE The increasing interest in the application of substantial quantities of radioisotopes for propulsion, energy conversion, and various other thermal concepts emphasizes a need for the most recent and most accurate information available describing the nuclear, chemical, and physical properties of these isotopes. A substantial amount of progress has been achieved in recent years in refining old and developing new techniques of measurement of the properties quoted, and isotope processing. This has resulted in a broad technological base from which both the material and information about the material is available. Un- fortunately, it has also resulted in a multiplicity of sources so that information and data are either untimely or present properties without adequately identifying the measurement techniques or describing the quality of material used. The purpose of this document is to make available, in a single reference, an annotated bibliography and sets of properties for nine of the more attractive isotopes available for use in power production. Part I contains all the unclassified information that was available in the literature surveyed. Part II is the classified counterpart to Part I. -
The Nuclear Fuel Cycle
THE COLLECTION > From the uranium mine> toI wNTasRtOeD dUisCpToIsOaN l 1 > The atom 2 > Radioactivity 3 > Radiation and man 4 > Energy 5 > Nuclear energy: fusion and fission 6 > How a nuclear reactor works 7 > The nuclear fuel cycle 7 > The nuclear fuel cycle FROM RESEARCH 8 > Microelectronics 9 > The laser: a concentrate of light TO INDUSTRY 10 > Medical imaging 11 > Nuclear astrophysics 12 > Hydrogen 7 >>TThhee nnuucclleeaarr ffuueell ccyyccllee UPSTREAM THE REACTOR: PREPARING THE FUEL IN THE REACTOR: FUEL CONSUMPTION DOWNSTREAM THE REACTOR: REPROCESSING NUCLEAR WASTE NUCLEAR WASTE © Commissariat à l’’Énergie Atomique et aux Energies Alternatives, 2005 Communication Division Bâtiment Siège - 91191 Gif-sur-Yvette cedex www.cea.fr ISSN 1637-5408. From the uranium mine to waste disposal 7 > The nuclear fuel cycle From the uranium mine to waste disposal 7 > The nuclear fuel cycle 2 > CONTENTS > INTRODUCTION 3 Uranium ore is extracted from open-pit mines – such as the McClear mines in Canada seen here – or underground workings. a m e g o C © “The nuclear fuel cycle includes an erray UPSTREAM THE REACTOR: of industrial operations, from uranium PREPARING THE FUEL 4 e mining to the disposal of radioactive l Extracting uranium from the ore 5 waste.” c Concentrating and refining uranium 6 y Enriching uranium 6 c Enrichment methods 8 l introduction uel is a material that can be burnt to pro - IN THE REACTOR: FUEL CONSUMPTION 9 Fvide heat. The most familiar fuels are wood, e Preparing fuel assemblies 10 coal, natural gas and oil. By analogy, the ura - e g a nium used in nuclear power plants is called Per unit or mass (e.g.