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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Main Authors: Mohammad Alrwashdeh, Saeed A. Alameri
Format: Article
Language:English
Published: AIP Publishing LLC 2019-07-01
Series:AIP Advances
Online Access:http://dx.doi.org/10.1063/1.5115807
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author Mohammad Alrwashdeh
Saeed A. Alameri
author_facet Mohammad Alrwashdeh
Saeed A. Alameri
author_sort Mohammad Alrwashdeh
collection DOAJ
description 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.
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spelling doaj.art-fbc54d2d29454d43a2d9e553bdd160d62022-12-21T23:42:25ZengAIP Publishing LLCAIP Advances2158-32262019-07-0197075112075112-610.1063/1.5115807054907ADVReactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactorMohammad Alrwashdeh0Saeed A. Alameri1Department of Nuclear Engineering, Khalifa University of Science and Technology, PO Box 127788, Abu Dhabi, United Arab EmiratesDepartment of Nuclear Engineering, Khalifa University of Science and Technology, PO Box 127788, Abu Dhabi, United Arab EmiratesTraditional 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.http://dx.doi.org/10.1063/1.5115807
spellingShingle Mohammad Alrwashdeh
Saeed A. Alameri
Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor
AIP Advances
title Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor
title_full Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor
title_fullStr Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor
title_full_unstemmed Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor
title_short Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor
title_sort reactor monte carlo rmc model validation and verification in compare with mcnp for plate type reactor
url http://dx.doi.org/10.1063/1.5115807
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AT saeedaalameri reactormontecarlormcmodelvalidationandverificationincomparewithmcnpforplatetypereactor