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Development of a passive safety shutdown device to prevent core damage accidents in fast reactors; performance of the device in reactivity control and nuclear material management
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- Sagara Hiroshi
- Tokyo Institute of Technology
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- Kawashima Masatoshi
- Tokyo Institute of Technology
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- Morita Koji
- Kyushu University
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- Liu Wei
- Kyushu University
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- Arima Tatsumi
- Kyushu University
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- Arita Yuji
- University of Fukui
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- Sato Isamu
- Tokyo City University
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- Matsuura Haruaki
- Tokyo City University
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- Sekio Yoshihiro
- Japan Atomic Energy Agency
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Description
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 objectives of the present paper are to evaluate the device in reactivity control based on design requirements for selecting candidate materials and specifications in anticipated transient without scram (ATWS) of a 750MWe class SFR, and the ex-core performance evaluation of the device fuel in nuclear material management. As results, based on the examination of the functions and roles of the device fuel during rated power operation, the reference specifications for the alloy-fueled device has been selected as ternary U-Pu-10at%Fe alloy with Pu enrichment of 25% in device fuel zone, and ternary U-Pu-10wt.%Zr alloy with Pu enrichment of 50% in preheating zone. With this reference device, reactivity control effectiveness was confirmed against unprotected loss of flow (ULOF) and unprotected transient overpower (UTOP) accidents. As for the ex-core performance in nuclear material management, the attractiveness of the device was evaluated as the same category of MOX fuel for states and non-state actors, no additional measures would be required in the reactor plant. Non-Destructive Assay (NDA) techniques would be significant for nuclear safeguards verification and for quality assurance.
Journal
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- Progress in Nuclear Science and Technology
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Progress in Nuclear Science and Technology 7 (0), 34-40, 2025-03-31
Atomic Energy Society of Japan
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Keywords
Details 詳細情報について
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- CRID
- 1390585492990766208
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- ISSN
- 21854823
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- Text Lang
- en
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- Data Source
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- JaLC
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- Abstract License Flag
- Disallowed