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AbstractAbstract
[en] In the use of nuclear techniques, one of the safety problems is the protection of personnel and delicate instruments against harmful radiation. It is therefore of prime importance that the designer of nuclear experiments have a basic understanding of how radiation behaves when it passes through matter. This is a tutorial paper that presents the fundamentals of electromagnetic radiation with respect to its interaction and absorption in matter. (author)
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PUSPATI, Selangor (Malaysia); 190 p; 1981; p. 163-176; Seminar on application of nuclear techniques in industry; Kuala Lumpur (Malaysia); 16-19 Nov 1981
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AbstractAbstract
[en] An approach to resolving some problems in nuclear geophysics which relate to heterogeneous media is presented. The theory is based on an effective parameters method, which enables a single scheme to be used for solving problems involving γ-ray and neutron sources. This paper is the first of two and deals specifically with the basic theory and γ-ray transport problems. (Author)
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AbstractAbstract
No abstract available
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Transactions of the American Nuclear Society 1975 annual meeting; New Orleans, LA; 8 Jun 1975; Published in summary form only.
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Transactions of the American Nuclear Society; v. 21 p. 528-529
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AbstractAbstract
No abstract available
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Nuclear Science and Technology. A Series of Monographs and Textbooks, No. 9; 1972; 191 p; Academic Press, Inc; New York
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Book
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AbstractAbstract
No abstract available
Original Title
Approximation de l'equation de transport
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Journal Article
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C. R., Ser. A; v. 277(13); p. 637-640
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AbstractAbstract
No abstract available
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Nuclear science and technology, Volume 9; 1972; 191 p; Academic Press, Inc; New York
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Book
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Humbert, P.
EPJ Web of Conferences, Proceedings of the 13. international conference on radiation shielding and 19. topical meeting of the radiation protection and shielding division of the American Nuclear Society - 2016
EPJ Web of Conferences, Proceedings of the 13. international conference on radiation shielding and 19. topical meeting of the radiation protection and shielding division of the American Nuclear Society - 2016
AbstractAbstract
[en] SGRD (Spectroscopy, Gamma rays, Rapid Deterministic) code is used to infer the dimensions of a one-dimensional model of a shielded gamma ray source. The method is based on the simulation of the un-collided leakage current of discrete gamma lines that are produced by nuclear decay. Experimentally, the unscattered gamma lines leakage current is obtained by processing high precision gamma spectroscopy measurements. The material thicknesses are computed with SGRD using a fast ray-tracing algorithm embedded in a non-linear multidimensional iterative optimization procedure that minimizes the error metric between calculated and measured signatures. For verification, numerical results on a test problem are presented. The test problem is a spherical natural shell surrounded by polyethylene (CH2) and an aluminium cover. The gamma source is due to uranium radioactive decay and 5 characteristic lines are chosen for the optimization. The comparison between the initial and the optimized gamma line spectra with measurement simulated by direct transport calculation shows that the optimization method works well
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Source
Malgavi, F.; Malouch, F.; Diop, C.M'B.; Miss, J.; Trama, J.C. (eds.); EDP Sciences, 17, Avenue du Hoggar, Parc d'Activite de Courtaboeuf, BP 112, F-91944 Les Ulis Cedex A (France); v. 153 [1590 p.]; 2017; p. 06011.p.1-06011.p.5; ICRS-13: 13. international conference on radiation shielding; Paris (France); 3-6 Oct 2016; RPSD-2016: 19. topical meeting of the radiation protection and shielding division of the American Nuclear Society; Paris (France); 3-6 Oct 2016; Available from doi: http://dx.doi.org/10.1051/epjconf/201715306011; 10 refs.; This record replaces 51039546
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Book
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Marghitu, V.
Institutul de Fizica Atomica, Bucharest (Romania)
Institutul de Fizica Atomica, Bucharest (Romania)
AbstractAbstract
[en] The paper presents the typical arrangement of radiation source, radiation counter and measured object, the gamma radiation transport in substance, the criterion and principles of design and the industrial equipment elaborated on the basis of this work. (C.M.)
Original Title
Contributii la proiectarea radiometrica a instalatiilor industriale cu surse izotopice inchise de radiatii gama, utilizate in masurare
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Summary form only.; Thesis (Ph. D.).
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Journal Article
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Studii si Cercetari de Fizica; v. 27(1); p. 3-22
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AbstractAbstract
No abstract available
Original Title
FORTRAN IV
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Jul 1973; 33 p
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AbstractAbstract
[en] The special case of a triangular transfer matrix relevant to multigroup neutron-transport theory is discussed. The theory developed for the slowing down of neutrons (or photons) reduces the multigroup problem to a sequence of one-group problems. Thus, in contrast to strictly numerical techniques, a method for multigroup theory that does not require increased computational time for thick slabs is made available. 8 refs
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Nuclear Science and Engineering; ISSN 0029-5639; 
; v. 78(4); p. 311-314
; v. 78(4); p. 311-314
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