Modeling and simulation of a TRIGA MARK-II research reactor using WIMSD-5B and CITATION codes.
Identifieur interne : 000554 ( Main/Exploration ); précédent : 000553; suivant : 000555Modeling and simulation of a TRIGA MARK-II research reactor using WIMSD-5B and CITATION codes.
Auteurs : K. Benaalilou [Maroc] ; T. El Bardouni [Maroc] ; Y. Boulaich [Maroc] ; H. El Yaakoubi [Maroc] ; E. Chham [Maroc] ; M. Lahdour [Maroc]Source :
- Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine [ 1872-9800 ] ; 2019.
Abstract
The main objective of this study is to analyse neutronic safety parameters of the Moroccan TRIGA Mark-II research reactor using the WIMSD-5B and CITATION computer codes. New 172-group libraries of multi-group constants for the lattice code WIMSD-5B have been generated for all isotopes presented in the TRIGA reactor core by processing nuclear data from ENDFB-VII.1, JENDL-4.0 and JEFF-3.1.1 using NJOY99. The lattice code WIMSD-5B was employed to generate multi-group cross sections in the suitable format that will be used by the 3-dimensional diffusion code CITATION. This later was used to calculate various neutronic safety parameters of the TRIGA Mark-II research reactor, such as reactivity excess and neutron fluxes profiles. The results of these calculations are compared to the results of Monte Carlo calculation based on MCNP code. A good agreement is achieved and the current computation scheme will be adopted for our further coupling neutronic/thermal-hydraulic study of the Moroccan TRIGA reactor.
DOI: 10.1016/j.apradiso.2019.01.034
PubMed: 30925365
Affiliations:
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Benaalilou</name><affiliation wicri:level="1"><nlm:affiliation>Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetouan, Morocco. Electronic address: Khalid.benaalilou@gmail.com.</nlm:affiliation><country xml:lang="fr">Maroc</country><wicri:regionArea>Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetouan</wicri:regionArea><wicri:noRegion>Faculty of Sciences of Tetouan</wicri:noRegion></affiliation></author><author><name sortKey="El Bardouni, T" sort="El Bardouni, T" uniqKey="El Bardouni T" first="T" last="El Bardouni">T. 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Chham</name><affiliation wicri:level="1"><nlm:affiliation>Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetouan, Morocco.</nlm:affiliation><country xml:lang="fr">Maroc</country><wicri:regionArea>Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetouan</wicri:regionArea><wicri:noRegion>Faculty of Sciences of Tetouan</wicri:noRegion></affiliation></author><author><name sortKey="Lahdour, M" sort="Lahdour, M" uniqKey="Lahdour M" first="M" last="Lahdour">M. Lahdour</name><affiliation wicri:level="1"><nlm:affiliation>Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetouan, Morocco.</nlm:affiliation><country xml:lang="fr">Maroc</country><wicri:regionArea>Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetouan</wicri:regionArea><wicri:noRegion>Faculty of Sciences of Tetouan</wicri:noRegion></affiliation></author></analytic><series><title level="j">Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine</title><idno type="eISSN">1872-9800</idno><imprint><date when="2019" type="published">2019</date></imprint></series></biblStruct></sourceDesc></fileDesc><profileDesc><textClass></textClass></profileDesc></teiHeader><front><div type="abstract" xml:lang="en">The main objective of this study is to analyse neutronic safety parameters of the Moroccan TRIGA Mark-II research reactor using the WIMSD-5B and CITATION computer codes. New 172-group libraries of multi-group constants for the lattice code WIMSD-5B have been generated for all isotopes presented in the TRIGA reactor core by processing nuclear data from ENDFB-VII.1, JENDL-4.0 and JEFF-3.1.1 using NJOY99. The lattice code WIMSD-5B was employed to generate multi-group cross sections in the suitable format that will be used by the 3-dimensional diffusion code CITATION. This later was used to calculate various neutronic safety parameters of the TRIGA Mark-II research reactor, such as reactivity excess and neutron fluxes profiles. The results of these calculations are compared to the results of Monte Carlo calculation based on MCNP code. A good agreement is achieved and the current computation scheme will be adopted for our further coupling neutronic/thermal-hydraulic study of the Moroccan TRIGA reactor.</div></front></TEI><affiliations><list><country><li>Maroc</li></country><region><li>Rabat-Salé-Kénitra</li></region><settlement><li>Rabat</li></settlement></list><tree><country name="Maroc"><noRegion><name sortKey="Benaalilou, K" sort="Benaalilou, K" uniqKey="Benaalilou K" first="K" last="Benaalilou">K. Benaalilou</name></noRegion><name sortKey="Boulaich, Y" sort="Boulaich, Y" uniqKey="Boulaich Y" first="Y" last="Boulaich">Y. Boulaich</name><name sortKey="Chham, E" sort="Chham, E" uniqKey="Chham E" first="E" last="Chham">E. Chham</name><name sortKey="El Bardouni, T" sort="El Bardouni, T" uniqKey="El Bardouni T" first="T" last="El Bardouni">T. El Bardouni</name><name sortKey="El Yaakoubi, H" sort="El Yaakoubi, H" uniqKey="El Yaakoubi H" first="H" last="El Yaakoubi">H. El Yaakoubi</name><name sortKey="Lahdour, M" sort="Lahdour, M" uniqKey="Lahdour M" first="M" last="Lahdour">M. Lahdour</name></country></tree></affiliations></record>Pour manipuler ce document sous Unix (Dilib)
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