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A punched-card library of neutron cross-sections and its use in the mechanized preparation of group cross-sections for use in Monte Carlo, Carlson S{sub n} and other multi-group neutronics calculations on high-speed computers

Conference:

Abstract

The AWRE punched-card library of neutron cross-sections is described together with associated IBM-7090 programmes which process this data to give group-averaged cross-sections for use in Monte Carlo, Carlson S{sub n} and other multi-group neutronics calculations. The methods developed to deal with both isotropic and anisotropic elastic scattering are described. These include the multi-group transport approximation and the full treatment of anisotropic scattering using the Legendre polynomial moments of the scattering transfer matrix. The principles of group-constant formation are considered and illustrated by describing systems of group constants suitable for fast-reactor calculations. Practical problems such as the empirical adjustment of group constants to reproduce integral results and the collapsing of a many-group set of constants to give a few-group set are discussed. (author) [French] L'auteur decrit le fichier de cartes perforees sur lesquelles on enregistre a l'Atomic Weapons Research Establishment (AWRE) les sections efficaces neutroniques ainsi que les programmes IBM-7090 associes qui sont employes pour le traitement de ces informations, en vue d'obtenir des sections efficaces moyennes par groupe pouvant servir aux calculs de neutroniques a plusieurs groupes, effectues a l'aide des methodes de Monte-Carlo, S{sub n} de Carlson et autres methodes. L'auteur expose ensuite les methodes mises au point roda  More>>
Authors:
Parker, K [1] 
  1. Atomic Weapons Research Establishment, Aldermaston (United Kingdom)
Publication Date:
Mar 15, 1962
Product Type:
Conference
Report Number:
IAEA-SM-18/20
Resource Relation:
Conference: Seminar on Physics of Fast and Intermediate Reactors, Vienna (Austria), 3-11 Aug 1961; Other Information: 9 refs, 1 tab; Related Information: In: Physics of Fast and Intermediate Reactors. V. I. Proceedings of the Seminar on the Physics of Fast and Intermediate Reactors. V. I| 500 p. Title in other languages: Fichier, a cartes perforees, de sections efficaces neutroniques: emploi dans la preparation de sections efficaces de groupes pour les calculs par les methodes de Monte-Carlo, S_n de Carlson et autres calculs neutroniques multigroupes sur calculatrices rapides; Biblioteka perforirovannykh kartochek sechenij nejtronov i ee primenenie dlya mekhaniziro-vannoj podgotovki usrednennykh po gruppam sechenij dlya ispol'zovaniya v vychisleniyakh po metodam Monte Karlo, Karlsona S_n i v drugikh mnogogruppovykh nejtronnykh vychisleniyakh na bystrodejstvuyushchi kh schetno-reshayushchi kh ustrojstvakh; Fichero de tarjetas perforadas de secciones eficaces neutronicas: su empleo en la preparacion mecanizada de secciones eficaces de grupos para trabajar con calculadoras rapidas segun los metodos de Montecarlo, S_n de Carlson y otros procedimientos de grupos multiples
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; ANISOTROPY; ELASTIC SCATTERING; FAST REACTORS; GROUP CONSTANTS; LEGENDRE POLYNOMIALS; MONTE CARLO METHOD; MULTIGROUP THEORY; NEUTRONS; NUCLEAR DATA COLLECTIONS; SPHERICAL HARMONICS METHOD; TRANSFER MATRIX METHOD
OSTI ID:
22076128
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA12S0193035049
Submitting Site:
INIS
Size:
page(s) 207-230
Announcement Date:
Mar 21, 2013

Conference:

Citation Formats

Parker, K. A punched-card library of neutron cross-sections and its use in the mechanized preparation of group cross-sections for use in Monte Carlo, Carlson S{sub n} and other multi-group neutronics calculations on high-speed computers. IAEA: N. p., 1962. Web.
Parker, K. A punched-card library of neutron cross-sections and its use in the mechanized preparation of group cross-sections for use in Monte Carlo, Carlson S{sub n} and other multi-group neutronics calculations on high-speed computers. IAEA.
Parker, K. 1962. "A punched-card library of neutron cross-sections and its use in the mechanized preparation of group cross-sections for use in Monte Carlo, Carlson S{sub n} and other multi-group neutronics calculations on high-speed computers." IAEA.
@misc{etde_22076128,
title = {A punched-card library of neutron cross-sections and its use in the mechanized preparation of group cross-sections for use in Monte Carlo, Carlson S{sub n} and other multi-group neutronics calculations on high-speed computers}
author = {Parker, K}
abstractNote = {The AWRE punched-card library of neutron cross-sections is described together with associated IBM-7090 programmes which process this data to give group-averaged cross-sections for use in Monte Carlo, Carlson S{sub n} and other multi-group neutronics calculations. The methods developed to deal with both isotropic and anisotropic elastic scattering are described. These include the multi-group transport approximation and the full treatment of anisotropic scattering using the Legendre polynomial moments of the scattering transfer matrix. The principles of group-constant formation are considered and illustrated by describing systems of group constants suitable for fast-reactor calculations. Practical problems such as the empirical adjustment of group constants to reproduce integral results and the collapsing of a many-group set of constants to give a few-group set are discussed. (author) [French] L'auteur decrit le fichier de cartes perforees sur lesquelles on enregistre a l'Atomic Weapons Research Establishment (AWRE) les sections efficaces neutroniques ainsi que les programmes IBM-7090 associes qui sont employes pour le traitement de ces informations, en vue d'obtenir des sections efficaces moyennes par groupe pouvant servir aux calculs de neutroniques a plusieurs groupes, effectues a l'aide des methodes de Monte-Carlo, S{sub n} de Carlson et autres methodes. L'auteur expose ensuite les methodes mises au point roda etudier la diffusion elastique, tant isotrope qu'anisotrope. Elles comprennent l'approximation de transport a plusieurs groupes, ainsi que le traitement complet de la diffusion anisotrope par les moments polynomiaux de Legendre de la matrice de transfert de la diffusion. L'auteur examine les principes de la formation des constantes de groupes; a titre d'illustration, il decrit les systemes de constantes de groupes qui se pretent aux calculs de reacteurs a neutrons rapides. Il expose quelques problemes pratiques, tels que l'ajustement empirique des constantes de groupes pour reproduire des mesures integrales et la simplification d'une serie de constantes pour un grand nombre de groupes en vue d'obtenir une serie de constantes pour un petit nombre de groupes. (author) [Spanish] La memoria describe el fichero de tarjetas perforadas sobre las que se registran en el Atomic Weapons Research Establishment (AWRE) las secciones eficaces neutronicas, asi como los programas correspondientes de la calculadora IBM-7090 que se emplean para la elaboracion de estos datos con miras a obtener promedios por grupo de secciones eficaces apropiadas para calculos neutronicos de grupos multiples por los metodos de Montecarlo, de S{sub n} de Carlson y otros procedimientos. El autor expone seguidamente los metodos desarrollados para estudiar la dispersion elastica isotropica y anisotropica. Comprenden la aproximacion de transporte de grupos multiples y el tratamiento completo de la dispersion anisotropica empleando los momentos polinomicos de Legendre de la matriz de transferencia por dispersion. El trabajo expone los principios de la formacion de constantes de grupo y, a titulo ilustrativo, describe sistemas de constantes de grupo que sirven para calculos de reactores rapidos. Analiza algunos problemas practicos como la adaptacion empirica de las constantes de grupo para reproducir resultados de mediciones integrales, y la reduccion de un sistema de constantes de muchos grupos a otro de pocos grupos. (author) [Russian] V doklade daetsya opisanie nakho-dyashchejsya v Nauchno-issledovatel'sko m tsentre po razrabotke atomnogo oruzhiya biblioteki perforirovannykh kartochek sechenij nejtronov sovmestno s programmami IBM 7090, kotorye obrabatyvayut ehti dannye dlya polucheniya usrednennykh po gruppam sechenij, kotorye ispol'zuyutsya v nejtronnykh vychisleniyakh po metodam Monte Karlo, Karlsona S{sub n} i v drugikh mnogogruppovykh vychisleniyakh. Opisyvayutsya metody, kasayushchiesya kak izotropnogo, tak i anizotropnogo uprugogo rasseyaniya. Oni vklyuchayut mnogogruppovoe transportnoe priblizhenie i polnuyu obrabotku anizotropnogo rasseyaniya, ispol'zuya momenty mnogochlena Lezhandra matritsy peredachi rasseyaniya. Printsipy obrazovaniya gruppovoj postoyannoj obsuzhdayutsya i illyustriruyutsya pri pomoshchi opisaniya sistem gruppovykh postoyannykh, podkhodyashchikh dlya raschetov reaktorov na bystrykh nejtronakh. Obsuzhdayutsya takie prakticheskie problemy, kak ehmpiricheskoe sogla- sovanie gruppovykh postoyannykh dlya vosproizvodstva integral'nykh rezul'tatov i prive-denie mnogogruppovoj sistemy postoyannykh k malogruppovoj sisteme. (author)}
place = {IAEA}
year = {1962}
month = {Mar}
}