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Title: AMPX-77: A modular code system for generating coupled multigroup neutron-gamma cross-section libraries from ENDF/B-IV and/or ENDF/B-V

Abstract

AMPX-77 is a modular system of computer programs that pertain to nuclear analyses, with a primary emphasis on tasks associated with the production and use of multigroup cross sections. AH basic cross-section data are to be input in the formats used by the Evaluated Nuclear Data Files (ENDF/B), and output can be obtained in a variety of formats, including its own internal and very general formats, along with a variety of other useful formats used by major transport, diffusion theory, and Monte Carlo codes. Processing is provided for both neutron and gamma-my data. The present release contains codes all written in the FORTRAN-77 dialect of FORTRAN and wig process ENDF/B-V and earlier evaluations, though major modules are being upgraded in order to process ENDF/B-VI and will be released when a complete collection of usable routines is available.

Authors:
; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (United States)
Sponsoring Org.:
DOE; USDOE, Washington, DC (United States)
OSTI Identifier:
6831636
Alternate Identifier(s):
OSTI ID: 6831636; Legacy ID: DE93005750
Report Number(s):
ORNL/CSD/TM-283
ON: DE93005750
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; MULTIGROUP THEORY; A CODES; CROSS SECTIONS; FORTRAN; GAMMA RADIATION; MONTE CARLO METHOD; NEUTRON TRANSPORT; NUCLEAR DATA COLLECTIONS; PHOTON TRANSPORT; SHIELDING; CALCULATION METHODS; COMPUTER CODES; ELECTROMAGNETIC RADIATION; IONIZING RADIATIONS; NEUTRAL-PARTICLE TRANSPORT; NEUTRON TRANSPORT THEORY; PROGRAMMING LANGUAGES; RADIATION TRANSPORT; RADIATIONS; TRANSPORT THEORY 663430* -- Nucleon-Induced Reactions & Scattering-- (1992-); 663600 -- Radiation Physics-- (1992-)

Citation Formats

Greene, N.M., Ford, W.E. III, Petrie, L.M., and Arwood, J.W. AMPX-77: A modular code system for generating coupled multigroup neutron-gamma cross-section libraries from ENDF/B-IV and/or ENDF/B-V. United States: N. p., 1992. Web. doi:10.2172/6831636.
Greene, N.M., Ford, W.E. III, Petrie, L.M., & Arwood, J.W. AMPX-77: A modular code system for generating coupled multigroup neutron-gamma cross-section libraries from ENDF/B-IV and/or ENDF/B-V. United States. doi:10.2172/6831636.
Greene, N.M., Ford, W.E. III, Petrie, L.M., and Arwood, J.W. Thu . "AMPX-77: A modular code system for generating coupled multigroup neutron-gamma cross-section libraries from ENDF/B-IV and/or ENDF/B-V". United States. doi:10.2172/6831636. https://www.osti.gov/servlets/purl/6831636.
@article{osti_6831636,
title = {AMPX-77: A modular code system for generating coupled multigroup neutron-gamma cross-section libraries from ENDF/B-IV and/or ENDF/B-V},
author = {Greene, N.M. and Ford, W.E. III and Petrie, L.M. and Arwood, J.W.},
abstractNote = {AMPX-77 is a modular system of computer programs that pertain to nuclear analyses, with a primary emphasis on tasks associated with the production and use of multigroup cross sections. AH basic cross-section data are to be input in the formats used by the Evaluated Nuclear Data Files (ENDF/B), and output can be obtained in a variety of formats, including its own internal and very general formats, along with a variety of other useful formats used by major transport, diffusion theory, and Monte Carlo codes. Processing is provided for both neutron and gamma-my data. The present release contains codes all written in the FORTRAN-77 dialect of FORTRAN and wig process ENDF/B-V and earlier evaluations, though major modules are being upgraded in order to process ENDF/B-VI and will be released when a complete collection of usable routines is available.},
doi = {10.2172/6831636},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1992},
month = {10}
}