Modeling the effect in of criticality from changes in key parameters for small High Temperature Nuclear Reactor (U-Battery�) using MCNP4C
The neutron transport code, Monte Carlo N-Particle (MCNP) which was wellkown as the gold standard in predicting nuclear reaction was used to model the small nuclear reactor core called �U-battery��, which was develop by the University of Manchester and Delft Institute of Technology. The paper introd...
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my.uniten.dspace-294112023-12-28T12:12:58Z Modeling the effect in of criticality from changes in key parameters for small High Temperature Nuclear Reactor (U-Battery�) using MCNP4C Pauzi A.M. 55812611200 Computer software Criticality (nuclear fission) Reactor cores Small nuclear reactors Cladding material Core configuration Gold standards Graphite matrix High temperature nuclear reactors Monte carlo n particles Neutron transport University of Manchester conference proceeding data set high temperature model validation nuclear power plant numerical model software standard (reference) High temperature reactors The neutron transport code, Monte Carlo N-Particle (MCNP) which was wellkown as the gold standard in predicting nuclear reaction was used to model the small nuclear reactor core called �U-battery��, which was develop by the University of Manchester and Delft Institute of Technology. The paper introduces on the concept of modeling the small reactor core, a high temperature reactor (HTR) type with small coated TRISO fuel particle in graphite matrix using the MCNPv4C software. The criticality of the core were calculated using the software and analysed by changing key parameters such coolant type, fuel type and enrichment levels, cladding materials, and control rod type. The criticality results from the simulation were validated using the SCALE 5.1 software by [1] M Ding and J L Kloosterman, 2010. The data produced from these analyses would be used as part of the process of proposing initial core layout and a provisional list of materials for newly design reactor core. In the future, the criticality study would be continued with different core configurations and geometries. � Published under licence by IOP Publishing Ltd. Final 2023-12-28T04:12:58Z 2023-12-28T04:12:58Z 2013 Conference paper 10.1088/1755-1315/16/1/012138 2-s2.0-84881098950 https://www.scopus.com/inward/record.uri?eid=2-s2.0-84881098950&doi=10.1088%2f1755-1315%2f16%2f1%2f012138&partnerID=40&md5=d27d0eb657e14d2462668c76317e702b https://irepository.uniten.edu.my/handle/123456789/29411 16 1 12138 All Open Access; Gold Open Access Institute of Physics Publishing Scopus |
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Computer software Criticality (nuclear fission) Reactor cores Small nuclear reactors Cladding material Core configuration Gold standards Graphite matrix High temperature nuclear reactors Monte carlo n particles Neutron transport University of Manchester conference proceeding data set high temperature model validation nuclear power plant numerical model software standard (reference) High temperature reactors |
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Computer software Criticality (nuclear fission) Reactor cores Small nuclear reactors Cladding material Core configuration Gold standards Graphite matrix High temperature nuclear reactors Monte carlo n particles Neutron transport University of Manchester conference proceeding data set high temperature model validation nuclear power plant numerical model software standard (reference) High temperature reactors Pauzi A.M. Modeling the effect in of criticality from changes in key parameters for small High Temperature Nuclear Reactor (U-Battery�) using MCNP4C |
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The neutron transport code, Monte Carlo N-Particle (MCNP) which was wellkown as the gold standard in predicting nuclear reaction was used to model the small nuclear reactor core called �U-battery��, which was develop by the University of Manchester and Delft Institute of Technology. The paper introduces on the concept of modeling the small reactor core, a high temperature reactor (HTR) type with small coated TRISO fuel particle in graphite matrix using the MCNPv4C software. The criticality of the core were calculated using the software and analysed by changing key parameters such coolant type, fuel type and enrichment levels, cladding materials, and control rod type. The criticality results from the simulation were validated using the SCALE 5.1 software by [1] M Ding and J L Kloosterman, 2010. The data produced from these analyses would be used as part of the process of proposing initial core layout and a provisional list of materials for newly design reactor core. In the future, the criticality study would be continued with different core configurations and geometries. � Published under licence by IOP Publishing Ltd. |
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55812611200 |
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55812611200 Pauzi A.M. |
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Conference paper |
author |
Pauzi A.M. |
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Pauzi A.M. |
title |
Modeling the effect in of criticality from changes in key parameters for small High Temperature Nuclear Reactor (U-Battery�) using MCNP4C |
title_short |
Modeling the effect in of criticality from changes in key parameters for small High Temperature Nuclear Reactor (U-Battery�) using MCNP4C |
title_full |
Modeling the effect in of criticality from changes in key parameters for small High Temperature Nuclear Reactor (U-Battery�) using MCNP4C |
title_fullStr |
Modeling the effect in of criticality from changes in key parameters for small High Temperature Nuclear Reactor (U-Battery�) using MCNP4C |
title_full_unstemmed |
Modeling the effect in of criticality from changes in key parameters for small High Temperature Nuclear Reactor (U-Battery�) using MCNP4C |
title_sort |
modeling the effect in of criticality from changes in key parameters for small high temperature nuclear reactor (u-battery�) using mcnp4c |
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Institute of Physics Publishing |
publishDate |
2023 |
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1806423359102124032 |
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13.211869 |