Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
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- 守田, 幸路
- 九州大学大学院工学研究院エネルギー量子工学部門
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- 劉, 維
- 九州大学大学院工学研究院エネルギー量子工学部門
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- 有馬, 立身
- 九州大学大学院工学研究院エネルギー量子工学部門
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- アリタ, ユウジ
- 福井大学
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- Sato, Isamu
- 東京都市大学
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- マツウラ, ハルアキ
- 東京都市大学
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- セキオ, ヨシヒロ
- 日本原子力研究開発機構
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- サガラ, ヒロシ
- 東京工業大学
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- カワシマ, マサシ
- 東京工業大学
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説明
A new subassembly type passive reactor shutdown device is proposed to expand the diversity and robustness of core disruptive accident prevention measures for sodium-cooled fast reactors (SFRs). The device contains pins with a fuel material that is in a solid state during normal operation but melts and fluidizes during an unprotected loss of flow (ULOF) or unprotected transient overpower (UTOP) accident. By rapidly transferring the liquefied device fuel into the lower plenum region of the pins via gravitation alone, the device passively provides high negative reactivity to the core. This study evaluated the nuclear and thermal properties of the device subassembly with metallic fuel to determine the device specifications for proper device operation during ULOF and UTOP accidents. The results of the transient analysis of the ULOF initiating phase in a 750-MWel-class mixed-oxide-fueled SFR core confirmed that a conventional homogeneous core maintains stable cooling of the core before coolant boiling in the driver fuel subassemblies. In contrast, the negative reactivity required to terminate the event by device operation was slightly higher in the low sodium void reactivity core than in the conventional homogeneous core.
収録刊行物
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- Journal of Nuclear Engineering and Radiation Science
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Journal of Nuclear Engineering and Radiation Science 9 (4), 041102-, 2023-03-14
ASME International
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詳細情報 詳細情報について
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- CRID
- 1050863329656967296
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- NII書誌ID
- AA12720749
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- ISSN
- 23328975
- 23328983
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- HANDLE
- 2324/7174404
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- 本文言語コード
- en
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- 資料種別
- journal article
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- データソース種別
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- IRDB