Fission and Corrosion Product Behaviour in Liquid Metal Fast Breeder Reactors (Lmfbrs)
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Volatility of Radiopharmacy-Prepared Sodium Iodide-131 Capsules
RADIATION SAFETY Volatility of Radiopharmacy-Prepared Sodium Iodide-131 Capsules James M. Bright, Trenton T. Rees, Louis E. Baca and Richard L. Green Pharmacy Services, Syncor International Corporation, Albuquerque, New Mexico; and Quality and Regulatory Department, Syncor International Corporation, Woodland Hills, California studied thyroid physiology using 128I in 1937 (1,2). In January Objective: The aims of this study were to quantify the extent 1941, Hertz and Roberts were the first to administer radioiodine of volatilization from 131I-NaI therapeutic capsules prepared in 131I for the treatment of hyperthyroid patients (3). Today, almost a centralized radiopharmacy and to quantify the amount of 60 y later, radioiodine therapy with 131I remains the primary volatile 131I released from a dispensing vial containing a compounded 131I-NaI therapy capsule. therapeutic agent used in nuclear medicine, and its use is firmly Methods: Therapy capsules were prepared by injecting 131I established in the 2 diseases first treated: hyperthyroidism and oral solution into capsules containing anhydrous dibasic thyroid carcinoma. sodium phosphate. Volatilized activity was obtained by filter- Initially the use of 131I was restricted to the only pharmaceu- ing air drawn across samples that were placed open on the tical dosage form then available—liquid oral solution. While 131 bottom of a sample holder cup. Volatile I was captured by liquid radioiodine proved to be beneficial to the patients to filtering it through 3 triethylenediamine-impregnated carbon whom it was administered, the frequency of contamination and cartridge filters, arranged in series. To quantify the amount of thyroid uptake activity in nuclear medicine personnel who volatile 131I released from a dispensing vial during a simulated patient administration, a vial containing a compounded 131I handled the material was noted with increasing alarm (4–7). -
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. -
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. -
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. -
Activation Analysis
26 August 1967 Leading Articles MEDIBALJOURNAL 509 her patients or the hospital midwife to undertake the home lation has been found between arsenic level in the blood and visiting of them after discharge. degree of renal insufficiency as indicated by blood creatinine Br Med J: first published as 10.1136/bmj.3.5564.509 on 26 August 1967. Downloaded from From the Bradford reports it can be seen that the final measurements. But speculative inquiries of this kind are decision to permit a mother and baby home after 48 hours worth while because they may sometimes provide the first must be made by someone at least of registrar status. It clue to the solution of an intractable problem. Information would also be of considerable value if the general practitioner of a more immediately useful kind can be expected from and district midwife in charge of such a case could freely using activation analysis in problems where the underlying obtain an opinion by domiciliary consultation from either the biochemical and physiological considerations are better hospital obstetric or paediatric department on any puerperal understood. or neonatal complication before readmission of the woman Thyroid metabolism, much studied by radioactive isotopes, after she has returned home. offers interesting problems for attack by activation analysis. When early discharge was discussed in these columns three Semi-automatic methods for the routine determination of years ago' the conclusion was drawn that, though it might protein-bound stable iodine have been elaborated, notably be suitable in emergency conditions, it had little part in in France,2 where the establishment of a laboratory to carry long-term planning. -
Arxiv:1708.07449V1 [Nucl-Ex] 24 Aug 2017
August 25, 2017 0:18 WSPC/INSTRUCTION FILE cosmogenics-ijmpa International Journal of Modern Physics A c World Scientific Publishing Company Cosmogenic activation of materials Susana Cebri´an Grupo de F´ısica Nuclear y Astropart´ıculas, Universidad de Zaragoza, Calle Pedro Cerbuna 12, 50009 Zaragoza, Spain Laboratorio Subterr´aneo de Canfranc, Paseo de los Ayerbe s/n 22880 Canfranc Estaci´on, Huesca, Spain [email protected] Received Day Month Year Revised Day Month Year Experiments looking for rare events like the direct detection of dark matter particles, neutrino interactions or the nuclear double beta decay are operated deep underground to suppress the effect of cosmic rays. But the production of radioactive isotopes in ma- terials due to previous exposure to cosmic rays is an hazard when ultra-low background conditions are required. In this context, the generation of long-lived products by cosmic nucleons has been studied for many detector media and for other materials commonly used. Here, the main results obtained on the quantification of activation yields on the Earth’s surface will be summarized, considering both measurements and calculations following different approaches. The isotope production cross sections and the cosmic ray spectrum are the two main ingredients when calculating this cosmogenic activation; the different alternatives for implementing them will be discussed. Activation that can take place deep underground mainly due to cosmic muons will be briefly commented too. Presently, the experimental results for the cosmogenic production of radioisotopes are scarce and discrepancies between different calculations are important in many cases, but the increasing interest on this background source which is becoming more and more relevant can help to change this situation. -
On the Calculation of the Fast Fission Factor
AE-27 On the Calculation of the w < Fast Fission Factor B. Almgren AKTIEBOLAGET ATOMENERGI STOCKHOLM • SWEDEN • I960 AE-27 ON THE CALCULATION OF THE FAST FISSION FACTOR E. Almgren Summary: Definitions of the fast fission factor e ars discussed. Different methods of calculation of e are compared. Group constants for one -, two- and three- group calculations have been evaluated using the best obtainable basic data. The effects of back-scattering, coupling and (n, 2n)-reactions are discussed. Completion of manuscript in June 1960 Printed and distributed in November 1960 LIST OF CONTENTS Page 1. Definitions 3 2. Formulas for the fast fission factor e and the fast fission ratio R 3 3. Calculation of group constants 7 4. Collision probabilities 10 5. Numerical results 12 6. Discussion 12 7. Acknowledgements 13 Preferences 14 On the calculation of the fast fission factor. 1. Definitions The fast fission factor e may be defined in different ways. Carlvik and Pershagen (3) have defined e as "the number of neutrons which are either slowed down below 0, 1 MeV in the fuel or leave the fuel, per primary neu- tron from thermal fission". This definition has been used in Sweden, since it was proposed (1956). Another commonly used definition is due to Spinrad (2) "the number of neutrons making first collision with moderator per neutron arising from thermal fission". The choice of definition must be consistent with the definition of the resonance escape probability. The above-mentioned definitions include in e some of the capture below the fast fission threshold. However, they do not include the effects of (n, 2n)-reactions or capture of high energy neutrons in the moderator. -
Etude Des Évolutions Microstructurales Sous Irradiation De L’Alliage D’Aluminium 6061-T6
THÈSE Pour obtenir le grade de DOCTEUR DE L’UNIVERSITÉ GRENOBLE ALPES Spécialité : Matériaux, Mécanique, Génie Civil, Electrochimie (2MGE) Arrêté ministériel : 7 août 2006 Présentée par Camille FLAMENT Thèse dirigée par Alexis DESCHAMPS et codirigée par Jérôme GARNIER et Joël RIBIS préparée au sein du Laboratoire d’étude du Comportement Mécanique des Matériaux (CEA) dans l'École Doctorale Ingénierie, Matériaux, Mécanique, Energétique, Environnement, Procédés, Production (I-MEP2) Etude des évolutions microstructurales sous irradiation de l’alliage d’aluminium 6061-T6 Thèse soutenue publiquement le 01 décembre 2015, devant le jury composé de : M. Alexis DESCHAMPS Professeur à l’INP de Grenoble, Directeur Mme. Myriam DUMONT Maître de conférences à l’Université Aix-Marseille, Rapporteur M. Thierry EPICIER Directeur de recherche au CNRS, Président M. Jérôme GARNIER Ingénieur de recherche au CEA, Co-encadrant M. Alexandre LEGRIS Professeur à l’Université Lille 1, Rapporteur M. Joël RIBIS Ingénieur de recherche au CEA, Co-encadrant REMERCIEMENTS Remerciements Cette thèse a été réalisée au Service de Recherches Métallurgiques Appliquées (SRMA) du Département des Matériaux pour le Nucléaire du CEA Saclay (DMN). Je souhaite donc tout d’abord remercier Messieurs Philippe Chapelot et Pascal Yvon de m’avoir accueillie respectivement au SRMA et DMN. Je remercie également Madame Laetitia Nicolas, ex-chef du Laboratoire d’étude du Comportement Mécanique des Matériaux qui fut mon laboratoire de rattachement et Monsieur Jean- Luc Béchade, ex-chef du Laboratoire d’Analyse Microstructurale des Matériaux (dorénavant chef du Service de Recherche de Métallurgie Physique) au sein duquel j’ai pu m’installer et utiliser les différents outils de caractérisation.