DIFF--A 7090 Fortran Program to Determine Neutron Diffusion Constants Relating to a Six-Group Calculation; DIFF--UN PROGRAMME FOR TRAN 7090 POUR DETERMINER LES CONSTANTES DE DIFFUSION NEUTRONIQUE RELATIVES A UN CALCUL A SIX GROUPES
Technical Report
·
OSTI ID:4713702
The computer program DIFF, in Fortran for the IBM 7090, for calculating the neutron diffusion coefficients and attenuation areas (L/sup 2/) necessary for multigroup diffusion calculations for reactor shielding is described. Diffusion coefficients and values of the inverse attenuation length are given for a six group calculation for several interesting shielding materials. (D.C.W.)
- Research Organization:
- European Atomic Energy Community. Nuclear Research Center, Ispra, Italy
- NSA Number:
- NSA-17-028220
- OSTI ID:
- 4713702
- Report Number(s):
- EUR-106.f
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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The Fortran Program for the Calculation of the Absorption and Double Scattering Corrections in Cross-Section Measurements with Fast Neutrons Using the Monte-Carlo Method; PROGRAMME FORTRAN POUR LE CALCUL DES CORRECTIONS D'ABSORPTION ET DE DOUBLE DIFFUSION DANS LES MESURES DE SECTIONS EFFICACES POUR LES NEUTRONS RAPIDES PAR LA METHODE DE MONTE-CARLO
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OSTI ID:4713702