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Computer code ANISN multiplying media and shielding calculation II. Code description (input/output)

Miscellaneous:

Abstract

The user manual of the ANISN computer code describing input and output subroutines is presented. ANISN code was developed to solve one-dimensional transport equation for neutron or gamma rays in slab, sphere or cylinder geometry with general anisotropic scattering. The solution technique is the discrete ordinate method. (M.C.K.).
Authors:
Publication Date:
Dec 31, 1990
Product Type:
Miscellaneous
Report Number:
INIS-BR-3085
Reference Number:
SCA: 990200; PA: AIX-24:008010; SN: 93000932766
Resource Relation:
Other Information: PBD: 1990
Subject:
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; A CODES; COMPUTER PROGRAM DOCUMENTATION; COMPUTER CALCULATIONS; DISCRETE ORDINATE METHOD; MANUALS; ONE-DIMENSIONAL CALCULATIONS; SHIELDING; TRANSPORT THEORY; 990200; MATHEMATICS AND COMPUTERS
OSTI ID:
10118338
Research Organizations:
Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)
Country of Origin:
Brazil
Language:
English
Other Identifying Numbers:
Other: ON: DE93612917; TRN: BR9230512008010
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
[49] p.
Announcement Date:
Jun 30, 2005

Miscellaneous:

Citation Formats

Maiorino, J R. Computer code ANISN multiplying media and shielding calculation II. Code description (input/output). Brazil: N. p., 1990. Web.
Maiorino, J R. Computer code ANISN multiplying media and shielding calculation II. Code description (input/output). Brazil.
Maiorino, J R. 1990. "Computer code ANISN multiplying media and shielding calculation II. Code description (input/output)." Brazil.
@misc{etde_10118338,
title = {Computer code ANISN multiplying media and shielding calculation II. Code description (input/output)}
author = {Maiorino, J R}
abstractNote = {The user manual of the ANISN computer code describing input and output subroutines is presented. ANISN code was developed to solve one-dimensional transport equation for neutron or gamma rays in slab, sphere or cylinder geometry with general anisotropic scattering. The solution technique is the discrete ordinate method. (M.C.K.).}
place = {Brazil}
year = {1990}
month = {Dec}
}