A neutronic investigation of tristructural isotropic-duplex fuel in a high-temperature reactor prismatic seed-and-blanket fuel block configuration with reduced power peaking

Combustion; Fuels; High temperature engineering; Monte Carlo methods; Oxide minerals; Thoria; Uranium dioxide; High temperature engineering test reactors; Monte carlo n particles; Multiplication factor; Neutron flux distributions; Neutronic analysis; Power Optimization; Reactor modeling; Reference m...

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Main Authors: Rabir M.H., Ismail A.F., Yahya M.S.
Other Authors: 55898782000
Format: Article
Published: John Wiley and Sons Ltd 2023
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spelling my.uniten.dspace-259452023-05-29T17:05:41Z A neutronic investigation of tristructural isotropic-duplex fuel in a high-temperature reactor prismatic seed-and-blanket fuel block configuration with reduced power peaking Rabir M.H. Ismail A.F. Yahya M.S. 55898782000 29067828200 56287449000 Combustion; Fuels; High temperature engineering; Monte Carlo methods; Oxide minerals; Thoria; Uranium dioxide; High temperature engineering test reactors; Monte carlo n particles; Multiplication factor; Neutron flux distributions; Neutronic analysis; Power Optimization; Reactor modeling; Reference modeling; High temperature reactors This paper presents the neutronic analysis of a tristructural isotropic (TRISO)-duplex fuel loaded into the high-temperature reactor (HTR) prismatic fuel block designs for a seed-and-blanket (S&B) reactor model. The selected fuel block design is the simplified model of a representative fuel configuration for the gas turbine�module helium reactor (GT-MHR) and high-temperature engineering test reactor (HTTR). The duplex fuel pellet comprises of UO2 as the seed and ThO2 as the blanket and uses the TRISO fuels. Monte Carlo N-particle extended (MCNPX) simulations were conducted to analyze the power and neutron flux distributions of the reference fuel block and that of the TRIOS-loaded duplex fuel designs. Standard neutronic parameters were computed, such as burnup-dependent infinite multiplication factors (kinf), average block spectrum, and fissile inventory. It was discovered that while the S&B model could attain the highest burnup and the longest cycle duration, its power peaking was more than threefolds than that of the reference model at the beginning of the cycle (BOC). The results also show that the �Duplex-2� model could reduce its power peaking by 24% through the integration of S&B arrangement with the duplex rods. It is noted that spatial distribution of the UO2 seed and 235U enrichment are the chief determining factors in the power optimization of the heterogeneous HTR prismatic fuel blocks loaded with thorium. � 2021 John Wiley & Sons Ltd. Final 2023-05-29T09:05:41Z 2023-05-29T09:05:41Z 2021 Article 10.1002/er.7021 2-s2.0-85109613356 https://www.scopus.com/inward/record.uri?eid=2-s2.0-85109613356&doi=10.1002%2fer.7021&partnerID=40&md5=3f0e541d606d39712b50bb9657fc70b3 https://irepository.uniten.edu.my/handle/123456789/25945 45 13 19265 19288 John Wiley and Sons Ltd 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/
description Combustion; Fuels; High temperature engineering; Monte Carlo methods; Oxide minerals; Thoria; Uranium dioxide; High temperature engineering test reactors; Monte carlo n particles; Multiplication factor; Neutron flux distributions; Neutronic analysis; Power Optimization; Reactor modeling; Reference modeling; High temperature reactors
author2 55898782000
author_facet 55898782000
Rabir M.H.
Ismail A.F.
Yahya M.S.
format Article
author Rabir M.H.
Ismail A.F.
Yahya M.S.
spellingShingle Rabir M.H.
Ismail A.F.
Yahya M.S.
A neutronic investigation of tristructural isotropic-duplex fuel in a high-temperature reactor prismatic seed-and-blanket fuel block configuration with reduced power peaking
author_sort Rabir M.H.
title A neutronic investigation of tristructural isotropic-duplex fuel in a high-temperature reactor prismatic seed-and-blanket fuel block configuration with reduced power peaking
title_short A neutronic investigation of tristructural isotropic-duplex fuel in a high-temperature reactor prismatic seed-and-blanket fuel block configuration with reduced power peaking
title_full A neutronic investigation of tristructural isotropic-duplex fuel in a high-temperature reactor prismatic seed-and-blanket fuel block configuration with reduced power peaking
title_fullStr A neutronic investigation of tristructural isotropic-duplex fuel in a high-temperature reactor prismatic seed-and-blanket fuel block configuration with reduced power peaking
title_full_unstemmed A neutronic investigation of tristructural isotropic-duplex fuel in a high-temperature reactor prismatic seed-and-blanket fuel block configuration with reduced power peaking
title_sort neutronic investigation of tristructural isotropic-duplex fuel in a high-temperature reactor prismatic seed-and-blanket fuel block configuration with reduced power peaking
publisher John Wiley and Sons Ltd
publishDate 2023
_version_ 1806424226112995328
score 13.211869