AMPX: a modular code system for generating coupled multigroup neutron-gamma libraries from ENDF/B
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)
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7342486
- Report Number(s):
- ORNL/TM-3706
- Country of Publication:
- United States
- Language:
- English
Similar Records
User's manual for the CDC-6600 version of AMPX
Advanced Neutron Source Cross Section Libraries (ANSL-V): ENDF/B-V based multigroup cross-section libraries for advanced neutron source (ANS) reactor studies
AMPX-77: A modular code system for generating coupled multigroup neutron-gamma cross-section libraries from ENDF/B-IV and/or ENDF/B-V
Technical Report
·
Mon Oct 31 23:00:00 EST 1977
·
OSTI ID:5297157
Advanced Neutron Source Cross Section Libraries (ANSL-V): ENDF/B-V based multigroup cross-section libraries for advanced neutron source (ANS) reactor studies
Technical Report
·
Sat Sep 01 00:00:00 EDT 1990
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OSTI ID:6502303
AMPX-77: A modular code system for generating coupled multigroup neutron-gamma cross-section libraries from ENDF/B-IV and/or ENDF/B-V
Technical Report
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Thu Oct 01 00:00:00 EDT 1992
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OSTI ID:6831636
Related Subjects
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
A CODES
BARYON REACTIONS
COMPUTER CODES
COMPUTER GRAPHICS
COUPLING
CROSS SECTIONS
ELECTROMAGNETIC RADIATION
GAMMA RADIATION
GAMMA TRANSPORT THEORY
HADRON REACTIONS
IONIZING RADIATIONS
MULTIGROUP THEORY
NEUTRON REACTIONS
NEUTRON TRANSPORT THEORY
NUCLEAR REACTIONS
NUCLEON REACTIONS
PHOTONUCLEAR REACTIONS
RADIATIONS
TRANSPORT THEORY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
A CODES
BARYON REACTIONS
COMPUTER CODES
COMPUTER GRAPHICS
COUPLING
CROSS SECTIONS
ELECTROMAGNETIC RADIATION
GAMMA RADIATION
GAMMA TRANSPORT THEORY
HADRON REACTIONS
IONIZING RADIATIONS
MULTIGROUP THEORY
NEUTRON REACTIONS
NEUTRON TRANSPORT THEORY
NUCLEAR REACTIONS
NUCLEON REACTIONS
PHOTONUCLEAR REACTIONS
RADIATIONS
TRANSPORT THEORY