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Neutronics calculation of the conceptual TRISO duplex fuel rod design

Cylinders (shapes); High temperature reactors; Light water reactors; Oxide minerals; Thoria; Uranium dioxide; Annular fuel; Fissile materials; Fuel design; Fuel rod design; Fuel rods; Light water; Neutronics; Neutronics performance; Fuels

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Main Authors: Rabir M.H., Ismail A.F., Yahya M.S.
Other Authors: 55898782000
Format: Article
Published: Elsevier Ltd 2023
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id my.uniten.dspace-26176
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spelling my.uniten.dspace-261762023-05-29T17:07:28Z Neutronics calculation of the conceptual TRISO duplex fuel rod design Rabir M.H. Ismail A.F. Yahya M.S. 55898782000 29067828200 56287449000 Cylinders (shapes); High temperature reactors; Light water reactors; Oxide minerals; Thoria; Uranium dioxide; Annular fuel; Fissile materials; Fuel design; Fuel rod design; Fuel rods; Light water; Neutronics; Neutronics performance; Fuels The duplex fuel pellet includes UO2 components as seed and ThO2 blanket, originally designed to increase the breeding rate of fissile materials in light water breeder reactors. However, the seed portion alone concentrates most of the energy released from the fission reaction, which can make the seed temperature too high. The duplex fuel potential for the high-temperature reactor (HTR) using TRISO fuel has never been researched. MCNPX simulation was conducted to compare the neutronics performance of normal TRISO fuel with that of TRISO duplex fuel. Two types of HTR fuel rod, the cylinder and the annular rod, were simulated and compared to see whether the duplex neutron characteristics would be better in the cylinder or annular fuel compact design. The TRISO duplex rods produced higher burnup than normal rods up to 5% higher for cylinder and 6% for annular rods. The TRISO duplex rod is also capable of maintaining longer criticality, producing smaller kinf changes and reducing the potential for plutonium build-up. The proposed TRISO duplex conceptual fuel design has an interesting neutronic properties, which offers possibilities for future studies. � 2021 The Author(s) Final 2023-05-29T09:07:28Z 2023-05-29T09:07:28Z 2021 Article 10.1016/j.nme.2021.101005 2-s2.0-85104600796 https://www.scopus.com/inward/record.uri?eid=2-s2.0-85104600796&doi=10.1016%2fj.nme.2021.101005&partnerID=40&md5=50f0d102c4c2e5953b6af96f33630441 https://irepository.uniten.edu.my/handle/123456789/26176 27 101005 All Open Access, Gold Elsevier 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 Cylinders (shapes); High temperature reactors; Light water reactors; Oxide minerals; Thoria; Uranium dioxide; Annular fuel; Fissile materials; Fuel design; Fuel rod design; Fuel rods; Light water; Neutronics; Neutronics performance; Fuels
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.
Neutronics calculation of the conceptual TRISO duplex fuel rod design
author_sort Rabir M.H.
title Neutronics calculation of the conceptual TRISO duplex fuel rod design
title_short Neutronics calculation of the conceptual TRISO duplex fuel rod design
title_full Neutronics calculation of the conceptual TRISO duplex fuel rod design
title_fullStr Neutronics calculation of the conceptual TRISO duplex fuel rod design
title_full_unstemmed Neutronics calculation of the conceptual TRISO duplex fuel rod design
title_sort neutronics calculation of the conceptual triso duplex fuel rod design
publisher Elsevier Ltd
publishDate 2023
_version_ 1806427766467330048
score 13.211869

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