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RIFIFI: Analytical calculation method of the critical condition and flux in a varied regions reactor by two-group theory and one dimension developed for the Mercury-Ferranti computer; Rififi: methode de calcul analytique de la condition critique et des flux d'une pile a regions variees en theorie a deux groupes et a une dimension programmee pour le calculateur electronique Mercury (Ferranti)

Abstract

The calculation method presented in this report has been developed for the Mercury-Ferranti computer of the C.E.N.S. This calculation method allows to resolve the diffusion equations and continuity equations of flux and flow with two groups of neutrons and one dimension in spherical, cylindrical and linear geometry. In the cylindrical and linear configurations, we can take the height and extrapolated radius into account. The critical condition can be realised by varying linearly one or more parameters: k{sub {infinity}}, medium frontier, height or extrapolated radius. The calculation method enables also to calculate the flux, adjoint flux and various integrals. In the first part, it explains what is needed to know before using the method: data presentation, method possibilities, results presentation with some information about restrictions, accuracy and calculation time. The complete formulation of the calculation method is given in the second part. (M.P.)
Authors:
Amouyal, A; Bacher, P; Lago, B; Mengin, F L; Parker, E [1] 
  1. Commissariat a l'Energie Atomique, Saclay (France).Centre d'Etudes Nucleaires
Publication Date:
Jul 01, 1960
Product Type:
Technical Report
Report Number:
CEA-R-1398
Resource Relation:
Other Information: 4 refs
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; ADJOINT FLUX; ANALYTICAL SOLUTION; CALCULATION METHODS; COMPUTERS; CONTINUITY EQUATIONS; CRITICALITY; CROSS SECTIONS; DATA PROCESSING; EXTRAPOLATION LENGTH; GEOMETRY; INTEGRAL CALCULUS; MULTI-PARAMETER ANALYSIS; MULTIGROUP THEORY; MULTIPLICATION FACTORS; NEUTRON DIFFUSION EQUATION
OSTI ID:
20942991
Research Organizations:
CEA Saclay, 91 - Gif-sur-Yvette (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR07R1398096444
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
33 pages
Announcement Date:
Dec 13, 2007

Citation Formats

Amouyal, A, Bacher, P, Lago, B, Mengin, F L, and Parker, E. RIFIFI: Analytical calculation method of the critical condition and flux in a varied regions reactor by two-group theory and one dimension developed for the Mercury-Ferranti computer; Rififi: methode de calcul analytique de la condition critique et des flux d'une pile a regions variees en theorie a deux groupes et a une dimension programmee pour le calculateur electronique Mercury (Ferranti). France: N. p., 1960. Web.
Amouyal, A, Bacher, P, Lago, B, Mengin, F L, & Parker, E. RIFIFI: Analytical calculation method of the critical condition and flux in a varied regions reactor by two-group theory and one dimension developed for the Mercury-Ferranti computer; Rififi: methode de calcul analytique de la condition critique et des flux d'une pile a regions variees en theorie a deux groupes et a une dimension programmee pour le calculateur electronique Mercury (Ferranti). France.
Amouyal, A, Bacher, P, Lago, B, Mengin, F L, and Parker, E. 1960. "RIFIFI: Analytical calculation method of the critical condition and flux in a varied regions reactor by two-group theory and one dimension developed for the Mercury-Ferranti computer; Rififi: methode de calcul analytique de la condition critique et des flux d'une pile a regions variees en theorie a deux groupes et a une dimension programmee pour le calculateur electronique Mercury (Ferranti)." France.
@misc{etde_20942991,
title = {RIFIFI: Analytical calculation method of the critical condition and flux in a varied regions reactor by two-group theory and one dimension developed for the Mercury-Ferranti computer; Rififi: methode de calcul analytique de la condition critique et des flux d'une pile a regions variees en theorie a deux groupes et a une dimension programmee pour le calculateur electronique Mercury (Ferranti)}
author = {Amouyal, A, Bacher, P, Lago, B, Mengin, F L, and Parker, E}
abstractNote = {The calculation method presented in this report has been developed for the Mercury-Ferranti computer of the C.E.N.S. This calculation method allows to resolve the diffusion equations and continuity equations of flux and flow with two groups of neutrons and one dimension in spherical, cylindrical and linear geometry. In the cylindrical and linear configurations, we can take the height and extrapolated radius into account. The critical condition can be realised by varying linearly one or more parameters: k{sub {infinity}}, medium frontier, height or extrapolated radius. The calculation method enables also to calculate the flux, adjoint flux and various integrals. In the first part, it explains what is needed to know before using the method: data presentation, method possibilities, results presentation with some information about restrictions, accuracy and calculation time. The complete formulation of the calculation method is given in the second part. (M.P.)}
place = {France}
year = {1960}
month = {Jul}
}