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Title: AMPX: a modular code system for generating coupled multigroup neutron-gamma libraries from ENDF/B

Abstract

AMPX is a modular system for producing coupled multigroup neutron-gamma cross section sets. Basic neutron and gamma cross-section data for AMPX are obtained from ENDF/B libraries. Most commonly used operations required to generate and collapse multigroup cross-section sets are provided in the system. AMPX is flexibly dimensioned; neutron group structures, and gamma group structures, and expansion orders to represent anisotropic processes are all arbitrary and limited only by available computer core and budget. The basic processes provided will (1) generate multigroup neutron cross sections; (2) generate multigroup gamma cross sections; (3) generate gamma yields for gamma-producing neutron interactions; (4) combine neutron cross sections, gamma cross sections, and gamma yields into final ''coupled sets''; (5) perform one-dimensional discrete ordinates transport or diffusion theory calculations for neutrons and gammas and, on option, collapse the cross sections to a broad-group structure, using the one-dimensional results as weighting functions; (6) plot cross sections, on option, to facilitate the ''evaluation'' of a particular multigroup set of data; (7) update and maintain multigroup cross section libraries in such a manner as to make it not only easy to combine new data with previously processed data but also to do it in a single pass on themore » computer; and (8) output multigroup cross sections in convenient formats for other codes. (auth)« less

Authors:
; ; ; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., Tenn. (USA)
OSTI Identifier:
7342486
Report Number(s):
ORNL/TM-3706
TRN: 08-019794
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; COMPUTER CODES; A CODES; GAMMA TRANSPORT THEORY; NEUTRON REACTIONS; CROSS SECTIONS; NEUTRON TRANSPORT THEORY; PHOTONUCLEAR REACTIONS; COMPUTER GRAPHICS; COUPLING; GAMMA RADIATION; MULTIGROUP THEORY; BARYON REACTIONS; ELECTROMAGNETIC RADIATION; HADRON REACTIONS; IONIZING RADIATIONS; NUCLEAR REACTIONS; NUCLEON REACTIONS; RADIATIONS; TRANSPORT THEORY; 654003* - Radiation & Shielding Physics- Neutron Interactions with Matter

Citation Formats

Greene, N.M., Lucius, J.L., Petrie, L.M., Ford, W.E. III, White, J.E., and Wright, R.Q.. AMPX: a modular code system for generating coupled multigroup neutron-gamma libraries from ENDF/B. United States: N. p., 1976. Web. doi:10.2172/7342486.
Greene, N.M., Lucius, J.L., Petrie, L.M., Ford, W.E. III, White, J.E., & Wright, R.Q.. AMPX: a modular code system for generating coupled multigroup neutron-gamma libraries from ENDF/B. United States. doi:10.2172/7342486.
Greene, N.M., Lucius, J.L., Petrie, L.M., Ford, W.E. III, White, J.E., and Wright, R.Q.. Mon . "AMPX: a modular code system for generating coupled multigroup neutron-gamma libraries from ENDF/B". United States. doi:10.2172/7342486. https://www.osti.gov/servlets/purl/7342486.
@article{osti_7342486,
title = {AMPX: a modular code system for generating coupled multigroup neutron-gamma libraries from ENDF/B},
author = {Greene, N.M. and Lucius, J.L. and Petrie, L.M. and Ford, W.E. III and White, J.E. and Wright, R.Q.},
abstractNote = {AMPX is a modular system for producing coupled multigroup neutron-gamma cross section sets. Basic neutron and gamma cross-section data for AMPX are obtained from ENDF/B libraries. Most commonly used operations required to generate and collapse multigroup cross-section sets are provided in the system. AMPX is flexibly dimensioned; neutron group structures, and gamma group structures, and expansion orders to represent anisotropic processes are all arbitrary and limited only by available computer core and budget. The basic processes provided will (1) generate multigroup neutron cross sections; (2) generate multigroup gamma cross sections; (3) generate gamma yields for gamma-producing neutron interactions; (4) combine neutron cross sections, gamma cross sections, and gamma yields into final ''coupled sets''; (5) perform one-dimensional discrete ordinates transport or diffusion theory calculations for neutrons and gammas and, on option, collapse the cross sections to a broad-group structure, using the one-dimensional results as weighting functions; (6) plot cross sections, on option, to facilitate the ''evaluation'' of a particular multigroup set of data; (7) update and maintain multigroup cross section libraries in such a manner as to make it not only easy to combine new data with previously processed data but also to do it in a single pass on the computer; and (8) output multigroup cross sections in convenient formats for other codes. (auth)},
doi = {10.2172/7342486},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1976},
month = {3}
}