ICONE19-43507 THERMAL ASPECTS OF USING ThO_2 IN A 54- AND 64-ELEMENT FUEL BUNDLE DESIGNED FOR SCWR APPLICATION
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- King Krysten
- Faculty of Energy Systems and Nuclear Science University of Ontario Institute of Technology
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- Abdalla Ayman
- Faculty of Energy Systems and Nuclear Science University of Ontario Institute of Technology
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- Qureshi Arif
- Faculty of Energy Systems and Nuclear Science University of Ontario Institute of Technology
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- Draper Shona
- Faculty of Energy Systems and Nuclear Science University of Ontario Institute of Technology
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- Peiman Wargha
- Faculty of Energy Systems and Nuclear Science University of Ontario Institute of Technology
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- Pioro Igor
- Faculty of Energy Systems and Nuclear Science University of Ontario Institute of Technology
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- Joel Jon
- Faculty of Engineering University of Waterloo
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- Gabriel Kamiel
- Faculty of Engineering and Applied Science University of Ontario Institute of Technology
抄録
The development of SuperCritical Water-cooled Reactors (SCWRs) is currently undertaken worldwide as part of the Generation-IV International Forum (GIF) initiative. SCWRs will operate at high operating temperatures and pressures: outlet temperatures up to 625℃ and pressures of 25 MPa. Since the development of SCWRs is in the conceptual-design stage, there are still various design issues that need to be addressed. The fuel-bundle configuration is not yet finalized; however, bundles with larger number of elements coupled with smaller element outside diameters seem to be preferred for use in SCWRs due to high fuel centerline temperatures. The most recent bundle designs for pressure channel SCWRs consists of 54 and 64 elements in total. The 54-element bundle has 53 heated fuelled elements (9.5-mm OD), and the 64-element bundle has 63 heated fuelled elements (9.13-mm OD). Both bundle designs have one unheated central element (20-mm OD). These new fuel bundles with Thoria fuel were analyzed. Thoria nuclear fuel, also known as Thorium dioxide (ThO_2), is currently considered as the primary choice in some SCWRs. The objective of this study is to examine the possibility of using Thoria as the nuclear fuel in SCWRs. Also, Thoria possesses a slightly higher thermal conductivity compared to that of Uranium dioxide (UO_2), which may help to decrease the fuel centerline temperature. Additionally, thorium is widely distributed in nature and is approximately three times as abundant as Uranium.
収録刊行物
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- Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE
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Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE 2011.19 (0), _ICONE1943-_ICONE1943, 2011
一般社団法人 日本機械学会
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詳細情報 詳細情報について
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- CRID
- 1390001205879883136
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- NII論文ID
- 110009956936
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- ISSN
- 24242934
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可