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MCNP benchmark analyses of critical experiments for the Space Nuclear Thermal Propulsion program

Conference · · AIP Conference Proceedings (American Institute of Physics); (United States)
DOI:https://doi.org/10.1063/1.43154· OSTI ID:6541704
; ; ; ; ;  [1];  [2]; ;  [3]
  1. Brookhaven National Laboratory, Reactor Systems Division, Bldg. 701, Upton, New York 11973 (United States)
  2. Sandia National Laboratories, P.O. Box 5800, Albuquerque, New Mexico 87185-5800 (United States)
  3. Babcock Wilcox Company - ASE, P.O. Box 10935, Lynchburg, Virginia 24506-10935 (United States)
+ Show Author Affiliations

Benchmark analyses have been performed of Particle Bed Reactor (PBR) critical experiments (CX) using the MCNP radiation transport code. The experiments have been conducted at the Sandia National Laboratory reactor facility in support of the Space Nuclear Thermal Propulsion (SNTP) program. The test reactor is a nineteen element water moderated and reflected thermal system. A series of integral experiments have been carried out to test the capabilities of the radiation transport codes to predict the performance of PBR systems. MCNP was selected as the preferred radiation analysis tool for the benchmark experiments. Comparison between experimental and calculational results indicate close agreement. This paper describes the analyses of benchmark experiments designed to quantify the accuracy of the MCNP radiation transport code for predicting the performance characteristics of PBR reactors.

DOE Contract Number:
AC02-76CH00016
OSTI ID:
6541704
Report Number(s):
CONF-930103--
Journal Information:
AIP Conference Proceedings (American Institute of Physics); (United States), Journal Name: AIP Conference Proceedings (American Institute of Physics); (United States) Vol. 271:2; ISSN 0094-243X; ISSN APCPCS
Country of Publication:
United States
Language:
English

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