Whole core neutronics modeling of a TRIGA reactor using integral transport theory

Conference · Thu Mar 01 04:00:00 EST 1990

OSTI ID:7172196

Schwinkendorf, K N; Toffer, H

An innovative analysis approach for performing whole core reactor physics calculations for TRIGA reactors has been employed recently at the Westinghouse Hanford Company. A deterministic transport theory model with sufficient geometric complexity to evaluate asymmetric loading patterns was used. Calculations of this complexity have been performed in the past using Monte Carlo simulation, such as the MCNP code. However, the Monte Carlo calculations are more difficult to prepare and require more computer time. On the Hanford Site CRAY XMP-18 computer, the new methods required less than one-third of the central processing unit time per calculation as compared to an MCNP calculation using 100,000 neutron histories. 4 refs., 4 figs., 2 tabs.

• Research Organization: Westinghouse Hanford Co., Richland, WA (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 7172196
• Report Number(s): WHC-SA-0865; CONF-9003102--1; ON: DE90008479
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
COMPARATIVE EVALUATIONS
COMPUTER CODES
COMPUTERIZED SIMULATION
COMPUTERS
CRAY COMPUTERS
CRITICALITY
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
IRRADIATION REACTORS
LOADING
M CODES
MATERIALS HANDLING
MATERIALS TESTING REACTORS
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
SOLID HOMOGENEOUS REACTORS
TESTING
TRIGA TYPE REACTORS
TRIGA-1-HANFORD REACTOR
TWO-DIMENSIONAL CALCULATIONS
VERIFICATION
W CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS