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Title: Contribution to the validation of MCNP neutronics design of the advanced neutron source reactor

In the research and development plan of the advanced neutron source (ANS) reactor, one of the steps planned for neutronics design methods validation is to compare computational model results and experimental results for a critical facility exhibiting similarities with the ANS reactor. One such facility is the FOEHN experiment. In this paper, an MCNP model of the FOEHN experiment is developed, and its results are compared with experimental data from the literature. The MCNP models reproduces measured quantities of interest with a high level of agreement.
Authors:
; ; ;  [1]
  1. (Idaho National Engineering Lab., Idaho Falls (United States))
Publication Date:
OSTI Identifier:
5802904
Report Number(s):
CONF-930601--
Journal ID: ISSN 0003-018X; CODEN: TANSAO
Resource Type:
Conference
Resource Relation:
Journal Name: Transactions of the American Nuclear Society; (United States); Journal Volume: 68; Conference: American Nuclear Society (ANS) annual meeting, San Diego, CA (United States), 20-24 Jun 1993
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; REACTOR PHYSICS; MATHEMATICAL MODELS; REACTORS; COMPUTERIZED SIMULATION; DESIGN; MONTE CARLO METHOD; NEUTRON SOURCES; REACTOR CORES; VALIDATION; CALCULATION METHODS; PARTICLE SOURCES; PHYSICS; RADIATION SOURCES; REACTOR COMPONENTS; SIMULATION; TESTING 220600* -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors; 220100 -- Nuclear Reactor Technology-- Theory & Calculation