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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Format: | Article |
Language: | English |
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AIP Publishing LLC
2019-07-01
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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. |
first_indexed | 2024-12-13T14:12:45Z |
format | Article |
id | doaj.art-fbc54d2d29454d43a2d9e553bdd160d6 |
institution | Directory Open Access Journal |
issn | 2158-3226 |
language | English |
last_indexed | 2024-12-13T14:12:45Z |
publishDate | 2019-07-01 |
publisher | AIP Publishing LLC |
record_format | Article |
series | AIP Advances |
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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