Rchr
J-GLOBAL ID:202101002255264415
Update date: Feb. 29, 2024
Kakiuchi Kazuo
カキウチ カズオ | Kakiuchi Kazuo
Affiliation and department:
Research field (1):
Nuclear engineering
Papers (15):
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Taniguchi Yoshinori, Mihara Takeshi, Kakiuchi Kazuo, Udagawa Yutaka. High-temperature rupture failure of high-burnup LWR-MOX fuel under a reactivity-initiated accident condition. Annals of Nuclear Energy. 2024. 195. 110144\_1-110144\_11
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Narukawa Takafumi, Kondo Keietsu, Fujimura Yuki, Kakiuchi Kazuo, Udagawa Yutaka, Nemoto Yoshiyuki. Behavior of FeCrAl-ODS cladding tube under loss-of-coolant accident conditions. Journal of Nuclear Materials. 2023. 582. 154467\_1-154467\_12
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Mihara Takeshi, Kakiuchi Kazuo, Taniguchi Yoshinori, Udagawa Yutaka. Behavior of high-burnup BWR UO$_{2}$ fuel with additives under reactivity-initiated accident conditions. Journal of Nuclear Science and Technology. 2023. 60. 5. 512-525
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Ito Ayumi*, Yamashita Susumu, Tasaki Yudai, Kakiuchi Kazuo, Kobayashi Yoshinao*. Double diffusive dissolution model of UO$_{2}$ pellet in molten Zr cladding. Journal of Nuclear Science and Technology. 2023. 60. 4. 450-459
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Kakiuchi Kazuo, Amaya Masaki, Udagawa Yutaka. Engineering formulation of the irradiation growth behavior of zirconium-based alloys for light water reactors. Journal of Nuclear Materials. 2023. 573. 154110\_1-154110\_7
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MISC (4):
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Kakiuchi Kazuo, Udagawa Yutaka, Yamauchi Akihiro*. Mechanical property evaluation of Zircaloy cladding tube after LOCA-simulated experiment using nanoindentation method (Joint research). JAEA-Research 2022-001. 2022. 21
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Kakiuchi Kazuo. Fuel Safety Research Meeting 2019. Kaku Nenryo. 2019. 55-1. 21-24
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Kakiuchi Kazuo. Report of the 31st Summer Seminar of the Nuclear Fuel Division of the Atomic Energy Society of Japan. Kaku Nenryo. 2019. 55-1. 25-30
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Taniguchi Yoshinori, Kakiuchi Kazuo, Amaya Masaki. Fuel Safety Research Meeting 2018. Kaku Nenryo. 2019. 54-1. 16-19
Lectures and oral presentations (13):
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Irradiation growth behavior in zirconium-based alloy claddings for PWR
(6th Asian Zirconium Workshop (AZW))
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Evaluation of the behavior of FeCrAl-ODS cladding tube during loss-of-coolant accident
(事故耐性燃料開発に関するワークショップ)
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Analysis of smear samples at Unit 2 reactor building of Fukushima Daiichi NPS
(日本原子力学会2022年秋の大会)
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Study on the failure behavior of high-burnup fuels under reactivity initiated accident conditions (Analyses of the failure mode change observed on a PWR-MOX fuel and its occurrence condition)
(日本原子力学会2022年秋の大会)
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Evaluation of mechanical properties of fuel cladding tubes using nanoindentation
(令和3年度原子力規制庁技術基盤グループ-原子力機構安全研究・防災支援部門合同研究成果報告会)
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