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Technical Paper

Chemical Interactions Between UO2 and Zircaloy-4 from 1000 to 2000°C

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Pages 109-124 | Published online: 10 May 2017

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Kosuke Tanaka, Shuhei Miwa, Isamu Sato, Takashi Hirosawa, Shin-ichi Sekine, Masahiko Osaka, Hiroshi Obayashi & Shin-ichi Koyama. (2014) Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior. Journal of Nuclear Science and Technology 51:7-8, pages 876-885.
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A. Itoh, Y. Kobayashi, A. Suzuki, T. Sato, N. Shirasu, Y. Nagae & M. Kurata. (2020) Thermodynamic approach for determination of fuel relocation condition in severe accident progression. Journal of Nuclear Materials 529, pages 151925.
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Ronghua Chen, Yonglin Li, Kailun Guo, Wenxi Tian, Suizheng Qiu & G.H. Su. (2017) Numerical investigation on the dissolution kinetics of ZrO 2 by molten zircaloy using MPS method. Nuclear Engineering and Design 319, pages 117-125.
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