Design Concept of Fast Spectrum Pulse Reactor with Packed Core of Coated Dilute Fuel Particles
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- OBARA Toru
- Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
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- SEKIMOTO Hiroshi
- Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
書誌事項
- タイトル別名
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- Design Concept of Fast Spectrum Pulse Reactor with Packed Core of Coated Dilute Fuel Particle.
- Design Concept of Fast Spectrum Pulse R
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A fast neutron pulse reactor that can provide high neutron fluence with relatively short pulse half-width is proposed, which has a core constituted of uranium or plutonium nitride diluted with titanium nitride, formed into particles coated with titanium nitride and packed without moderator. Dilution of the fuel kernel is shown to enhance the neutron fluence obtainable within the allowable maximum fuel temperature. Titanium nitride possesses high heat capacity, which also enables large neutron fluence before attainment of the allowable maximum fuel temperature. As fuel, 233U and 239Pu have the advantage over 235U of permitting criticality to be attained with lower fuel enrichment. The maximum fluence obtainable with a fuel composition of 239Pu enriched to 0.6 and diluted to 0.11 (239PuN+238UN)/(239PuN+238UN+TiN) volume is 3×1016n/cm2, which is 50 times what has been indicated for a conventional fast pulse reactor. The pulse width is significantly longer than that of the above-mentioned conventional reactor, but if necessary it can be shortened down to roughly equal value by adopting non-diluted fuel, at the expense of only reducing by half the obtainable neutron fluence.
収録刊行物
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- Journal of Nuclear Science and Technology(日本原子力学会英文論文誌)
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Journal of Nuclear Science and Technology(日本原子力学会英文論文誌) 33 (7), 547-554, 1996
一般社団法人 日本原子力学会
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詳細情報 詳細情報について
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- CRID
- 1390001204095225088
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- NII論文ID
- 10002075077
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- NII書誌ID
- AA00703720
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- COI
- 1:CAS:528:DyaK28Xlt1Glsbg%3D
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- ISSN
- 18811248
- 00223131
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- NDL書誌ID
- 4060405
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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
- NDL
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