Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor

Traditional neutronics calculations and simulation behavior of plate type research reactors pose a challenge comparing with the conventional pressurized water reactors. This is due to its complex geometry, characteristics, heterogeneity, and neutron leakage that lead to modeling difficulties. The Re...

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Bibliographic Details
Published inAIP advances Vol. 9; no. 7; pp. 075112 - 075112-6
Main Authors Alrwashdeh, Mohammad, Alameri, Saeed A.
Format Journal Article
LanguageEnglish
Published Melville American Institute of Physics 01.07.2019
AIP Publishing LLC
Subjects
Computer simulation
Control rods
Pressurized water reactors
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Summary:Traditional neutronics calculations and simulation behavior of plate type research reactors pose a challenge comparing with the conventional pressurized water reactors. This is due to its complex geometry, characteristics, heterogeneity, and neutron leakage that lead to modeling difficulties. The Reactor Monte Carlo code (RMC) is employed in stochastic approach for the neutronic analysis in the plate type research reactor. The goal of this report is to examine the capability and validity of the model built using RMC and compare the results with a well-known Monte Carlo code such as MCNP. The results between RMC and MCNP are in a good agreement for effective multiplications factor (keff), radial power peaking factor, total power peaking factor, and integral and differential control rods worth.
ISSN:2158-3226
2158-3226
DOI:10.1063/1.5115807