Application of an Integrated PC-Based Neutronics Code System to Criticality Safety

Conference · Mon Sep 09 04:00:00 EDT 1991

OSTI ID:5245034

Briggs, J. B. ^[1]; Nigg, D. W. ^[1]

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1. EG and G Idaho, Inc., Idaho Falls, ID (United States)

An integrated system of neutronics and radiation transport software suitable for operation in an IBM PC-class environment has been under development at the Idaho National Engineering Laboratory (INEL) for the past four years. Nuclear cross-section data and resonance parameters are preprocessed from the Version 5 Evaluated Nuclear Data Files (ENDF/B-V) and supplied in a form suitable for use in a PC-based spectrum calculation and cross-section generation module. The cross-section module of the PC-based code system produces application-specific data libraries that can be used in various PC-based neutron transport and diffusion theory code modules. Some of the modules in the system are straightforward conversions of existing codes with a few improvements to allow more effective operation in the PC environment while other modules were specifically written for the PC code system. Four modules within the system are particularly useful for criticality safety applications: COMBINE/PC, a portable ENDF/B Version 5 neutron spectrum and cross-section generation program; KENO5A/PC, a three-dimensional Monte Carlo criticality module; ANISN/PC, a one-dimensional, discrete ordinates transport theory code; and DORT/PC, a two-dimensional, discrete ordinates transport theory code. A description of the codes and methods used in the analysis and the results of the benchmark critical experiments are presented in this paper. In general, excellent agreement was found between calculated and experimental results.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5245034
• Report Number(s): EGG-M-90534; CONF-910993--16; ON: DE91018752
• Country of Publication: United States
• Language: English

Related Subjects

220100* -- Nuclear Reactor Technology-- Theory & Calculation
220900 -- Nuclear Reactor Technology-- Reactor Safety
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
990200 -- Mathematics & Computers
A CODES
ACTINIDES
C CODES
COMPUTER CODES
COMPUTERS
CRITICALITY
CROSS SECTIONS
Codes and Method Descriptions
Criticality Safety Applications
D CODES
DIFFUSION
DIGITAL COMPUTERS
E CODES
ELEMENTS
FUEL ELEMENTS
FUEL RODS
IBM PC-Class Environment
K CODES
METALS
MICROCOMPUTERS
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
PERSONAL COMPUTERS
PHYSICS
PLUTONIUM
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTOR LATTICES
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
Results
SAFETY
TRANSURANIUM ELEMENTS
URANIUM
WATER COOLED REACTORS