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Ruby, S.L.; Gardner, D.G.
International Atomic Energy Agency, Vienna (Austria)
International Atomic Energy Agency, Vienna (Austria)
AbstractAbstract
[en] This report contains a selected bibliography on the nondestructive assay of irradiated and unirradiated reactor fuel assemblies. The report also includes a discussion and evaluation of these papers in the light of the problems presented by variations in enrichment, alloying, cladding, geometrical arrangement, etc., among the many kinds of fuel assemblies. Suggestions for further development work are made. (author)
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Secondary Subject
Source
Technical reports series; No. 1; 1959; 42 p; IAEA; Vienna (Austria); STI/DOC--10/1; ISBN 92-0-175059-5; 

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Book
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AbstractAbstract
[en] In September last year, the Japanese Government requested the International Atomic Energy Agency to supply three tons of natural uranium for a research reactor, and the Agency has now arranged for its sale to Japan. The metal will be supplied in ingot form and after fabrication it will be used as fuel in a reactor of the natural uranium, heavy water type. The uranium will be obtained from Canada and sold to Japan by IAEA. The Agency had invited tenders for its supply, and after considering the tenders received, the Agency's Board of Governors decided that the Canadian offer to the Agency of three tons of natural uranium free of charge should be accepted and that the selling price to Japan should be US $35. 50 per kilogramme. The price takes into account Article XIV/E of the Agency's Statute which says that the Agency shall establish a scale of charges (including those for storage and handling) for materials furnished to Member States, and that the scale shall be designed to produce revenues to meet expenses in connexion with materials acquired by the Agency and costs of materials and services provided by it under agreements with one or more members. This is the first operation of its kind to be undertaken by the Agency, and the reactor for which the supply is being made will be the first in Japan to be constructed by Japanese scientists and technicians. IAEA's Board of Governors has given the necessary approval to the reactor project for which the Agency is providing assistance
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Source
Available on-line: http://www.iaea.org/Publications/Magazines/Bulletin/Bull011/01104700506.pdf; 2 photos
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Journal Article
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AbstractAbstract
[en] The Scientific Advisory Committee of the International Atomic Energy Agency held its second series of meetings in Vienna on 4-5 June 1959. The members of the Committee are seven distinguished scientists from different countries: Dr. H.J. Bhabha (India), Sir John Cockcroft (UK), Professor V.S. Emelyanov (USSR), Dr. B. Goldschmidt (France), Dr. B. Gross (Brazil), Dr. W.B. Lewis (Canada) and Professor I.I. Rabi (USA). The function of the Committee is to provide the Director General and through him the Board of Governors with scientific and technical advice on questions relating to the Agency's activities. Subjects for consideration by the Committee can be submitted by the Director General either on his own behalf or on behalf of the Board. At its recent session, the Committee considered several aspects of the Agency's scientific programme, including the proposed conferences, symposia and seminars for 1960, scientific and technical publications, and the research contracts which had been or were to be awarded by the Agency. The programme of conferences for the current year had been approved earlier by the Board of Governors on the recommendation of the Committee. A provisional list of 17 conferences, symposia and seminars for 1960 was examined by the Committee and recommendations were made to the Director General. The Committee also examined the Agency's policy on the award of contracts for research work and studies. An important subject before the Committee was the principles and regulations for the application of Agency safeguards. Another subject considered by the Committee was the possibility of a project for an exchange of knowledge on controlled thermonuclear fusion. The Committee also examined a proposal for the determination of the world-wide distribution of hydrogen and oxygen isotopes in water. Exact information on the distribution of hydrogen and oxygen isotopes in rain, in rivers, in ground water and in oceans would be important for areas with limited water supply, and would add to the present knowledge of potential water resources in arid and semi-arid regions. Among other subjects considered by the Committee was the preparation of a basic manuscript on atomic energy and its peaceful uses, which could serve as an aid to teachers in secondary schools, particularly in the technically less advanced countries. The IAEA Board of Governors has already approved the project for such a manual, which will be prepared in co-operation with UNESCO
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Source
Available on-line: http://www.iaea.org/Publications/Magazines/Bulletin/Bull012/01205101314.pdf; 2 photos
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Journal Article
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AbstractAbstract
[en] In ''profile counting'', a counter is moved progressively along the whole length of the body, and is so collimated that, at each position, it records the radioisotope content of the whole width of the body, but of only a short section of its length. If the counting rate at each position is plotted against the distance of the counter from the vertex of the head, the ''profile'' so obtained gives a rapid and quantitative measure of the radioisotope distribution throughout the body. When a suitable isotope is selectively concentrated in certain organs or tissues of the body, the profile will show peaks indicative of the sites and extent of such concentration, the organs concerned being identified by two-dimensional mapping, and profile counts continued to follow the turnover or changes of concentration in these organs. This technique has been used in the study of I131 concentration and metabolism in thyroid carcinomata, and its value in the management of the radioiodine treatment of such tumours will be discussed. It has also been used in examining the distribution of labelled thyroxine and triiodothyronine after intravenous administration, and of yttrium-90 oxide particles after intrapulmonary artery injection; and of other isotopes by gamma radiation or bremsstrahlung. The method gives a clinically convenient simplification of whole body mapping which lends itself particularly to the quantitative comparison of isotope distribution at different intervals after a radioisotope dose, or after successive doses. (author)
[fr]
On deplace progressivement, le long du corps, un collimateur regle de maniere a deceler, dans chaque position, la quantite de radioisotopes contenue dans toute l'epaisseur du corps, mais sur un bref secteur seulement de sa longueur. Si l'on trace une courbe indiquant le taux de comptage en fonction de la distance entre le compteur et le sommet de la tete, on obtient un < profil> qui donne rapidement une mesure quantitative de la repartition des radioisotopes dans le corps. Quand un isotope approprie est concentre selectivement dans certains organes ou tissus du corps, le < profil> presente des pointes indiquant l'emplacement et les dimensions de ces concentrations, les organes affectes peuvent alors etre identifies au moyen de doubles visees; on poursuit le comptage le long de l'axe principal du corps, afin de suivre le debit ou les changements de concentration dans ces organes. Cette technique a ete mise en oeuvre pour etudier la concentration et le metabolisme de l'iode-131 dans les cancers de la thyroide; son utilite pour le mode de traitement de ces tumeurs au moyen du radioiode sera examinee. La meme technique a ete adoptee pour etudier la repartition de la thyroxine et de la triiodothyronine marquees apres injection intraveineuse et celle de particules d'oxyde d'yttrium-90 apres injection arterielle intrapulmonaire , ainsi que pour determiner la repartition d'autres isotopes d'apres l'irradiation gamma ou le rayonnement de freinage. Cette methode permet une simplification, utile en recherche clinique, du releve graphique complet du corps humain; elle se prete particulierement a la comparaison quantitative de la repartition des isotopes a des intervalles differents, apres une ou plusieurs doses successives de radioisotopes. (author)[es]
En el recuento segun el eje principal del cuerpo, se desplaza progresivarnente un contador a lo largo de todo el organismo, colimandolo de tal forma que, en cada posicion, registre la cantidad de radioisotopos contenida en toda la anchura del cuerpo y solamente en una pequena seccion de su longitud. Si se representa graficamente el indice de recuento en funcion de la distancia del contador a la parte superior de la cabeza, se obtiene un ''perfil'' que proporciona una medida rapida y cuantitativa de la distribucion de los radioisotopos en el organismo. Cuando un isotopo adecuado este concentrado de modo selectivo en determinados organos o tejidos del organismo, el perfil presentara maximos que indican las regiones del cuerpo en que se producen esas concentraciones y el grado de las mismas; los organos de que se trate pueden identificarse entonces mediante un sistema de representacion bidimensional; se prosigue luego el recuento segun el eje principal con el fin de observar la renovacion de los isotopos o las modificaciones de su concentracion en esos organos. Esta tecnica se ha utilizado para estudiar la concentracion y el metabolismo del yodo-131 en los tumores de la tiroides; se examinara su utilidad para vigilar el tratamiento de esos tumores con yodo radiactivo. La misma tecnica se ha empleado para estudiar la distribucion de la tiroxina y de la triyodotironina marcadas con yodo-131 administradas por via intravenosa, y de particulas de oxido de itrio-90, despues de su inyeccion en una arteria intrapulmonar, asi como para determinar la distribucion de otros isotopos sobre la base de la radiacion gamma o de la radiacion de frenado. Este metodo permite obtener una representacion grafica, convenientemente simplificada para diagnosis mediante comparaciones cuantitativas, de la distribucion, a diferentes intervalos, de los isotopos administrados en dosis unica o sucesivas. (author)[ru]
Pri takom issledovanii schetchik postepenno peremeshchaetsya vdol' vsego tela i tak kollimirovan, chto on v kazhdom polozhenii pokazyvaet soderzhanie radioizotopov lish' v uzkoj polose poperek vsego tela. Esli vychertit' diagrammu skorosti otschetov v kazhdom polozhenii v sootvetstvii s rasstoyaniem schetchika ot temeni, to poluchennaya takim obrazom krivaya pozvolyaaet bystroe izmerenie kolichestvennog o raspredeleni ya izotopov vo vsem tele. Kogda nadlezhashchij izotop preimushchestvenn o skontsentrirovals ya v nekotorykh organakh ili tkanyakh tela, to v krivoj poyavlyayutsya rezkie povysheniya, pokazyvayushchie mesto i razmery takoj kontsentratsii, prichem sootvetstvuyushchi e organy opoznayutsya putem sostavleniya skhemy v dvukh izmereniyakh, a issledovanie schetchikom prodolzhaetsya s tsel'yu sledit' za peremeshniem ili izmeneniem kontsentratsii v ehtikh organakh. EHtot metod byl ispol'zovan pri izuchenii kontsentratsii I131 i obmena veshchestv v rakovykh opukholyakh shchitovidnoj zhelezy, i predstoit obsudit' ego tsennost' dlya lecheniya takikh opukholej radioaktivny m iodom. On primenyalsya takzhe dlya izucheniya raspredeleniya mechenogo tiroksina i tijodotronina posle ikh vvedeniya v venu i chastits okisi ittriya90 posle vnutrilegochnoj arterial'noj infektsii, a takzhe drugikh izotopov s pomoshch'yu gamma i tormoznogo izlucheniya. EHtot metod uproshchaet, v udobnykh v klinicheskom otnoshenii usloviyakh, sostavlenie skhemy vsego tela, kotoraya, v chastnosti, pozvolyaet provesti kolichestvennoe sravnenie raspredeleniya izotopov v razlichnye promezhutki vremeni posle vvedeniya odnoj ili neskol'kikh posleduyushchikh doz radioizotopa. (author)Original Title
Comptage suivant l'axe principal du corps; Issledovanie schetchikom vdol' vsego tela; Recuento segun el eje principal del cuerpo
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International Atomic Energy Agency, Vienna (Austria); World Health Organization, Geneva (Switzerland); 278 p; 1959; p. 143-157; Seminar on Medical Radioisotope Scanning; Vienna (Austria); 25-27 Feb 1959; ISSN 0074-1884;
; 33 figs, 5 refs

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Book
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Conference
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AMINO ACIDS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BLOOD VESSELS, BODY, CARBOXYLIC ACIDS, CARDIOVASCULAR SYSTEM, DAYS LIVING RADIOISOTOPES, ELECTROMAGNETIC RADIATION, ENDOCRINE GLANDS, GLANDS, HORMONES, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, IODINE ISOTOPES, IONIZING RADIATIONS, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, NUCLEI, ODD-EVEN NUCLEI, ODD-ODD NUCLEI, ORGANIC ACIDS, ORGANIC COMPOUNDS, ORGANIC HALOGEN COMPOUNDS, ORGANIC IODINE COMPOUNDS, ORGANS, PEPTIDE HORMONES, PROTEINS, RADIATIONS, RADIOISOTOPES, THYROID HORMONES, YTTRIUM ISOTOPES
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AbstractAbstract
[en] The migration length M and the infinite multiplication factor k∞ of the heavy water-natural uranium bare assembly are determined by measuring the reactivity of the reactor as function of the heavy water level. Since the assembly is non reflected the results obtained are of relatively high accuracy. (author)
Primary Subject
Source
Bulletin of the Institute of Nuclear Sciences 'Boris Kidric; v. 9(169); Mar 1959; 5 p; Institute of Nuclear Sciences 'Boris Kidric'; Beograd-Vinca (Yugoslavia); Also available from the Institute of nuclear sciences Vinca; 5 refs., 2 figs.
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Miscellaneous
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Bazire, R.; Blin, J.; Cherel, G.; Duvaux, Y.; Cherel, G.; Mustelier, J.P.; Bussy, P.; Gondal, G.; Bloch, J.; Faugeras, P.; Raggenbass, A.; Raggenbass, P.; Fufresne, J.
CEA Saclay, 91 - Gif-sur-Yvette (France)
CEA Saclay, 91 - Gif-sur-Yvette (France)
AbstractAbstract
[en] Describes the conception and installation of the hot laboratory in Saclay (CEA, France). The construction ended in 1958. The main aim of this laboratory is to examine fuel rods of EL2 and EL3 as well as nuclear fuel studies. It is placed in between both reactors. In a first part, the functioning and specifications of the hot lab are given. The different hot cells are described with details of the ventilation and filtration system as well as the waste material and effluents disposal. The different safety measures are explained: description of the radiation protection, decontamination room and personnel monitoring. The remote handling equipment is composed of cutting and welding machine controlled with manipulators. Periscopes are used for sight control of the operation. In a second part, it describes the equipment of the hot lab. The unit for an accurate measurement of the density of irradiated uranium is equipped with an high precision balance and a thermostat. The equipment used for the working of irradiated uranium is described and the time length of each operation is given. There is also an installation for metallographic studies which is equipped with a manipulation bench for polishing and cleaning surfaces and a metallographic microscope. X-ray examination of uranium pellets will also be made and results will be compared with those of metallography. The last part describes the hot cells used for the manipulation of plutonium salts. The plutonium comes from the reprocessing plant and arrived as a nitric solution. Thus these cells are used to study the preparation of plutonium fluorides from nitric solution. The successive operations needed are explained: filtration, decontamination and extraction with TBP, purification on ion exchangers and finally formation of the plutonium fluorides. Particular attention has been given to the description of the specifications of the different gloveboxes and remote handling equipment used in the different reaction steps and manipulations. (M.P.)
Original Title
Laboratoire a tres haute activite de Saclay. Equipement et techniques radiometallurgiques du laboratoire a haute activite de Saclay. Description de cellules pour manipulation de sels de plutonium. Amenagement d'une cellule du laboratoire de haute activite
Primary Subject
Source
1959; 98 p; 6. Hot Lab. and Equipment Conference; Congres sur les laboratoires de haute activite; Chicago (United States); Mar 1958
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Report
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Conference
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ENGINEERING DRAWINGS, GLOVEBOXES, HOT CELLS, HOT LABS, MANIPULATORS, METALLOGRAPHY, MICROSCOPY, PERISCOPES, PLUTONIUM FLUORIDES, POLISHING, POST-IRRADIATION EXAMINATION, RADIATION PROTECTION, RADIOACTIVE WASTE PROCESSING, REMOTE HANDLING, REMOTE VIEWING EQUIPMENT, SAMPLE PREPARATION, SHIELDING, SPECIFICATIONS, SPENT FUEL ELEMENTS, VENTILATION SYSTEMS
ACTINIDE COMPOUNDS, DIAGRAMS, EQUIPMENT, FLUORIDES, FLUORINE COMPOUNDS, FUEL ELEMENTS, HALIDES, HALOGEN COMPOUNDS, INFORMATION, LABORATORIES, LABORATORY EQUIPMENT, MANAGEMENT, MATERIALS HANDLING EQUIPMENT, NUCLEAR FACILITIES, OPTICAL SYSTEMS, PLUTONIUM COMPOUNDS, PROCESSING, RADIOACTIVE WASTE MANAGEMENT, REACTOR COMPONENTS, REMOTE HANDLING EQUIPMENT, SURFACE FINISHING, TRANSURANIUM COMPOUNDS, WASTE MANAGEMENT, WASTE PROCESSING
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Jammet, H.; Perrissin, F.
CEA Saclay, 91 - Gif-sur-Yvette (France)
CEA Saclay, 91 - Gif-sur-Yvette (France)
AbstractAbstract
[en] These statistics deal with the doses due to external exposure received by the monitored workers of the French Atomic Centers and of other establishments. They allow: - to estimate the value of the accumulated doses with respect to the maximum permissible levels recommended by the I.C.R.P. and to follow their variation over some years. - to arrange the different categories of work by order of hazard with respect to the doses received by the workers while achieving the operations. - to come to the conclusion that it is possible to work in atomic industry without reaching the maximum permissible levels. (author)
[fr]
Ces statistiques portent sur les doses d'irradiation externe recues par le personnel surveille appartenant au Commissariat et a d'autres organismes. Elles permettent: - d'apprecier la valeur des doses cumulees en fonction des normes de la C.I.P.R. ainsi que leur evolution au cours des annees. - de classer les differentes categories de travaux par ordre de risque en fonction des doses recues pendant leur execution. - de conclure a la possibilite de travail dans l'industrie atomique sans que les doses maxima admissibles soient atteintes. (auteur)Original Title
Enseignement tire de l'examen des statistiques etablies a partir des archives radiologiques individuelles
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Source
1959; 16 p
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Report
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Numerical Data
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Allison, G.M.; Crocker, I.H.
Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)
Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)
AbstractAbstract
[en] A highly rated (∫ k.dθ = 48 W/cm) sintered UO2 specimen, 0.8 in. O.D., with a 0.010-in. diameter hole through the Zircaloy sheath, was irradiated in the X-2 loop in the NRX reactor for approximately 16 days. For this irradiation period the escape-rate coefficients calculated for the fission products Kr-88, Cs-138, I-135, I-133 and I-131 were similar to those found in previous defect tests on UO2 fuel operated at considerably lower heat ratings. The test was terminated due to high activity in the loop water which occurred during a reactor trip-startup cycle. Post-irradiation examination of the defected fuel element indicated no reason for the activity surge. (author)
Primary Subject
Source
Jun 1959; 28 p; EXP-NRX--1806; 17 refs., 8 tabs., 5 figs.
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Report
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ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, ISOTOPES, MATERIALS, MATERIALS TESTING REACTORS, NATURAL URANIUM REACTORS, OXIDES, OXYGEN COMPOUNDS, POWER REACTORS, PRESSURE TUBE REACTORS, RADIOACTIVE MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, URANIUM COMPOUNDS, URANIUM OXIDES, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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Depken, Sven
AB Atomenergi, Stockholm (Sweden)
AB Atomenergi, Stockholm (Sweden)
AbstractAbstract
[en] The neutron (one-velocity) angular distribution function is expanded in terms of spherical harmonic tensors. The solution to the equations of the moments is given explicitly and the result is applied to the plane, spherical and cylinder symmetrical cases
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Source
Mar 1959; 60 p
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Report
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Ekberg, Kim
AB Atomenergi, Stockholm (Sweden)
AB Atomenergi, Stockholm (Sweden)
AbstractAbstract
[en] For each natural element up to Bi this report gives: the 2200 m/sec neutron absorption cross section; the nuclides formed by thermal neutron activation; the saturation activity per gram natural element for a certain flux; half life and 'tenth life' of the activity; β-energy and/or type of decay; mean γ energy per disintegration; energy and abundance of γ quanta
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Source
May 1959; 36 p; 6 refs., 1 tab.
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Report
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