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Methods and experimental coefficients used in the computation of reactor shielding; Methodes et coefficients experimentaux pour le calcul des protections de reacteurs

Abstract

1. The concept of an effective removal cross section has been developed in order more easily to compute reactor shielding thicknesses. We have built an experimental facility for the purpose of measuring effective removal cross sections, the value of which had not been published at that time. The first part of this paper describes the device or facility used, the computation method applied, and the results obtained. 2. Starting from this concept, we endeavored to define a removal cross section as a function of energy. This enabled us to use the method for computations bearing on the attenuation of fast neutrons of any spectrum. An experimental verification was carried out for the case of fission neutrons filtered by a substantial thickness of graphite. 3. Finally, we outline a computation method enabling us to determine the sources of captured gamma rays by the age theory and we give an example of the application in a composite shield. (author)Fren. [French] 1. La notion de section efficace effective de deplacement a ete introduite pour calculer commodement les epaisseurs de protection des reacteurs. Nous avons construit un dispositif experimental destine a mesurer les sections efficaces effectives de deplacement dont la valeur n'avait pas ete  More>>
Authors:
Bourgeois, J; Lafore, P; Millot, J P; Rastoin, J; Vathaire, F de [1] 
  1. Commissariat a l'Energie Atomique, Saclay (France). Centre d'Etudes Nucleaires
Publication Date:
Jul 01, 1958
Product Type:
Technical Report
Report Number:
CEA-R-967
Resource Relation:
Other Information: 4 refs
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; BERYLLIUM OXIDES; COMPUTERIZED SIMULATION; CONCRETES; CROSS SECTIONS; FAST NEUTRONS; FISSION NEUTRONS; GAMMA RADIATION; GRAPHITE; IRON; LEGENDRE POLYNOMIALS; NEUTRON FLUX; RADIATION ABSORPTION ANALYSIS; REACTOR EXPERIMENTAL FACILITIES; SCALE MODELS; SHIELDING MATERIALS; SLOWING-DOWN; THERMAL NEUTRONS; THICKNESS
OSTI ID:
20901017
Research Organizations:
CEA Saclay, 91 - Gif-sur-Yvette (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR07R0967063240
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
38 pages
Announcement Date:
Aug 28, 2007

Citation Formats

Bourgeois, J, Lafore, P, Millot, J P, Rastoin, J, and Vathaire, F de. Methods and experimental coefficients used in the computation of reactor shielding; Methodes et coefficients experimentaux pour le calcul des protections de reacteurs. France: N. p., 1958. Web.
Bourgeois, J, Lafore, P, Millot, J P, Rastoin, J, & Vathaire, F de. Methods and experimental coefficients used in the computation of reactor shielding; Methodes et coefficients experimentaux pour le calcul des protections de reacteurs. France.
Bourgeois, J, Lafore, P, Millot, J P, Rastoin, J, and Vathaire, F de. 1958. "Methods and experimental coefficients used in the computation of reactor shielding; Methodes et coefficients experimentaux pour le calcul des protections de reacteurs." France.
@misc{etde_20901017,
title = {Methods and experimental coefficients used in the computation of reactor shielding; Methodes et coefficients experimentaux pour le calcul des protections de reacteurs}
author = {Bourgeois, J, Lafore, P, Millot, J P, Rastoin, J, and Vathaire, F de}
abstractNote = {1. The concept of an effective removal cross section has been developed in order more easily to compute reactor shielding thicknesses. We have built an experimental facility for the purpose of measuring effective removal cross sections, the value of which had not been published at that time. The first part of this paper describes the device or facility used, the computation method applied, and the results obtained. 2. Starting from this concept, we endeavored to define a removal cross section as a function of energy. This enabled us to use the method for computations bearing on the attenuation of fast neutrons of any spectrum. An experimental verification was carried out for the case of fission neutrons filtered by a substantial thickness of graphite. 3. Finally, we outline a computation method enabling us to determine the sources of captured gamma rays by the age theory and we give an example of the application in a composite shield. (author)Fren. [French] 1. La notion de section efficace effective de deplacement a ete introduite pour calculer commodement les epaisseurs de protection des reacteurs. Nous avons construit un dispositif experimental destine a mesurer les sections efficaces effectives de deplacement dont la valeur n'avait pas ete publiee a cette epoque. La premiere partie de cette communication decrit le dispositif utilise, la methode de calcul employee et les resultats obtenus. 2. A partir de cette notion, nous avons essaye de definir une section efficace de deplacement fonction de l'energie. Ceci permet d'utiliser la methode du deplacement pour des calculs d'attenuation de neutrons rapides dont le spectre est quelconque. Une verification experimentale a ete faite dans le cas de neutrons de fission filtres par une epaisseur notable de graphite. 3. Enfin une mde de calcul permettant de determiner les sources de gamma de capture par la theorie de l'age est exposee et un exemple d'application donne dans une protection composite. (auteur)}
place = {France}
year = {1958}
month = {Jul}
}