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AbstractAbstract
[en] Problems of standardization, design and production of radiation-shielding items are considered. Radiation-shielding items include systems and means providing for operation safety under harmful effects of ionizing radiation and radioactive substances on a person and prevention of possible environment contamination by radioactive substances according to permissible normals and rules
Original Title
Standartizatsiya i serijnoe proizvodstvo izdelij radiatsionno-zashchitnoj tekhniki
Primary Subject
Source
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (USSR). Tsentral'nyj Nauchno-Issledovatel'skij Inst. Informatsii i Tekhniko-Ehkonomicheskikh Issledovanij po Atomnoj Nauke i Tekhnike; Voprosy atomnoj nauki i tekhniki; no. 3; p. 47-51; 1987; p. 47-51; 5 refs.; 1 tab.
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Miscellaneous
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AbstractAbstract
[en] In all aspects related to the nuclear activity, the occurrence of an explosion, fire or burst type accident, with or without victims, is directly related to the characteristics of the site. The present work analyses the different parameters involved, describing a transference model and recommendations for evaluation and control of the radiological risk for firemen. Special emphasis is placed on the measurement of the variables existing in this kind of operations
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Secondary Subject
Source
International Radiation Protection Association, Washington, DC (USA); Australian Radiation Protection Society, Sydney (Australia); 3 v; ISBN 0 08 03441 0 (V.2);
; 1988; p. 1000-1003; Pergamon Press; Sydney (Australia); 7. international congress of the International Radiation Protection Association; Sydney (Australia); 10-17 Apr 1988

Record Type
Book
Literature Type
Conference
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Ilari, O.; Jouannaud, C.
Proceedings of the NEA seminar on the storage of spent fuel elements. Madrid, 20-23 June 19781978
Proceedings of the NEA seminar on the storage of spent fuel elements. Madrid, 20-23 June 19781978
AbstractAbstract
[en] The authors outline the current international co-operation connected with the safety of fuel cycle facilities, with particular reference to the safety of facilities for the storage of spent fuel. The view of the NEA/CSNI Working Group on the Safety of the Fuel Cycle are reported and the principal problems of the safety of fuel storage are reviewed in the perspective of the safety of the entire fuel cycle. It is concluded that the problems associated with short-term storage are well understood and managed, and that the additional problem of maintaining the integrity of fuel assemblies during long-term storage requires further research
Primary Subject
Secondary Subject
Source
Anon; p. 85-96; ISBN 92-64-01840-9;
; 1978; p. 85-96; OECD; Paris, France; Seminar on the storage of spent fuel elements; Madrid, Spain; 20 - 23 Jun 1978

Record Type
Book
Literature Type
Conference
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Bernavon, Jean; Renavot, J.-M.
CEA, 75 - Paris (France)1977
CEA, 75 - Paris (France)1977
AbstractAbstract
[en] Flask for handling a fuel assembly, comprising an internal sleeve placed coaxially with the assembly, fitted vertically in the flask and marking an intermediate space between the sleeves and the assembly for circulation on contact with the assembly by the natural convection of a liquid environment contained in the flask. It is characterised in that the sleeve has two parts in succession placed one after the other, the bottom part being made of a heat conducting material and the top part of a thermal insulation material
[fr]
Pot de manutention d'un assemblage combustible, comportant une chemise interne disposee coaxialement a l'assemblage monte verticalement dans le pot et delimitant un espace intermediaire entre la chemise et l'assemblage pour la circulation au contact de l'assemblage par convection naturelle d'un milieu liquide contenu dans le pot, caracterise en ce que ladite chemise comporte deux parties successives, placees dans le prolongement l'une de l'autre, la partie inferieure etant constituee d'un materiau conducteur de la chaleur et la partie superieure d'un materiau isolant thermiqueOriginal Title
Pot de manutention d'un assemblage combustible pour reacteur nucleaire
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Source
26 Jan 1977; 8 p; FR PATENT DOCUMENT 2379139/A/; Available from Institut National de la Propriete Industrielle, Paris (France)
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Patent
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AbstractAbstract
[en] Bayes' theorem is used to quantify the impact of new evidence in three energy-related decision problems. The first problem concerns the risk of radioactivity release during the railroad transport of spent nuclear fuel. This history of shipments thus far is shown to make it highly unlikely that the frequency of release is on the order of 10-3 or greater per shipment. The second and third applications involve predicting the availability performance of new generations of turbine blades. Bayes' theorem is demonstrated as a means for incorporating in the prediction the limited operational data on the new blades along with the experience of the earlier generation and the knowledge of the design changes
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Secondary Subject
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Journal Article
Journal
Nuclear Technology; ISSN 0029-5450;
; v. 44(2); p. 231-245

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AbstractAbstract
[en] A dry transport technique and its safe analysis for the HFETR discharged fuel elements transported within the plant are described and the results of transporting 32 boxes of HFETR discharged fuel elements of first loaded in the 5 MW LPR (Low Power Reactor) are also given
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Journal Article
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Cheverton, R.D.; Turner, W.D.
Oak Ridge National Lab., Tenn. (USA)1971
Oak Ridge National Lab., Tenn. (USA)1971
AbstractAbstract
No abstract available
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Source
Jun 1971; 27 p
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Report
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Hill, A.J.
Du Pont de Nemours (E.I.) and Co., Aiken, S.C. (USA). Savannah River Lab1971
Du Pont de Nemours (E.I.) and Co., Aiken, S.C. (USA). Savannah River Lab1971
AbstractAbstract
No abstract available
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Apr 1971; 140 p
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Report
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Nicholson, G.A.
Atlantic Richfield Hanford Co., Richland, Wash. (USA)1970
Atlantic Richfield Hanford Co., Richland, Wash. (USA)1970
AbstractAbstract
No abstract available
Primary Subject
Source
1 Jul 1970; 15 p; 63. national meeting of the American Institute of Chemical Engineers; Chicago, Ill; 29 Nov 1970; CONF-701103--2
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Report
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Klima, B.B.; Shappert, L.B.
Oak Ridge National Lab., Tenn. (USA)1971
Oak Ridge National Lab., Tenn. (USA)1971
AbstractAbstract
No abstract available
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Source
Nov 1971; 41 p
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Report
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