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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Main Author: Pauzi A.M.
Other Authors: 55812611200
Format: Conference paper
Published: Institute of Physics Publishing 2023
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spelling 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
institution Universiti Tenaga Nasional
building UNITEN Library
collection Institutional Repository
continent Asia
country Malaysia
content_provider Universiti Tenaga Nasional
content_source UNITEN Institutional Repository
url_provider http://dspace.uniten.edu.my/
topic 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
spellingShingle 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
description 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.
author2 55812611200
author_facet 55812611200
Pauzi A.M.
format Conference paper
author Pauzi A.M.
author_sort 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
publisher Institute of Physics Publishing
publishDate 2023
_version_ 1806423359102124032
score 13.211869