Verification of MCNP6 model of the Jordan Research and Training Reactor (JRTR) for calculations of neutronic parameters

•A new computational model has been developed and validated for JRTR using MCNP6.•The effect of the operating temperature was considered by applying pseudo materials method.•Important neutronics parameters for the JRTR initial core were compared with reference values.•The MCNP6 results were in a goo...

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Bibliographic Details
Published in:Annals of nuclear energy 2016-10, Vol.96, p.96-103
Main Authors: Jaradat, Mustafa K., Radulović, Vladimir, Park, Chang Je, Snoj, Luka, Alkhafaji, Salih M.
Format: Article
Language:English
Subjects:
Computer simulation
Criticality
Enrichment
Flux
JRTR
Keff
Mathematical models
MCNP6
Monte Carlo
Monte Carlo methods
Neutronic
Nuclear engineering
Nuclear power generation
Nuclear reactor components
Nuclear reactors
Power peaking factor
Research reactor
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Summary:•A new computational model has been developed and validated for JRTR using MCNP6.•The effect of the operating temperature was considered by applying pseudo materials method.•Important neutronics parameters for the JRTR initial core were compared with reference values.•The MCNP6 results were in a good agreement with reference results in the safety analysis report.•This model will be used to study the neutronic characteristics of the irradiation holes of JRTR. The Jordan Research and Training Reactor (JRTR) is a multi-purpose reactor with power of 5MW currently under commissioning. The core consists of standard MTR plate type fuel assemblies with low enriched fuel of 19.75% U-235 enrichment. A new computational model has been developed for JRTR using the MCNP6 Monte Carlo code. The purpose of this paper is to validate the MCNP6 model by comparison of the calculation results of important neutronics parameters like keff, flux distribution, kinetics parameters, power peaking factors, and control rod worth to the reference results which were obtained by the McCARD Monte Carlo code and presented in the safety analysis report. Same modeling assumptions were adopted in the MCNP6 model in order to check the computational differences. In addition various up-to-date nuclear data libraries were used in calculations to assess their effect on calculated quantities. The calculation results showed good agreement and the difference in the effective multiplication factor is up 50pcm.
ISSN:0306-4549
1873-2100
DOI:10.1016/j.anucene.2016.06.003