Whole core neutronics modeling of a TRIGA reactor using integral transport theory
Conference
·
OSTI ID:21141211
- Westinghouse Hanford Company, Richland, WA (United States)
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.
- Research Organization:
- General Atomics, San Diego, CA (United States)
- OSTI ID:
- 21141211
- Report Number(s):
- INIS-US--09N0043; WHC-SA--0865-FP; Contract DE-AC06-87RL10930
- Country of Publication:
- United States
- Language:
- English
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