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Journal of Nuclear Science and Technology Volume 60, 2023 - Issue 6
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Article

Cost-reduced depletion calculation including short half-life nuclides for nuclear fuel cycle simulation

Tomohiro Okamuraa Laboratory for Zero-Carbon Energy, Institute of Innovative Research, Tokyo Institute of Technology, TokyoJapanCorrespondence[email protected] [email protected]
ORCID Iconhttps://orcid.org/0000-0002-9754-8114View further author information
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Ryota Katanob Nuclear Science Research Institute, Sector of Nuclear Science Research, Japan Atomic Energy Agency, IbarakiJapanORCID Iconhttps://orcid.org/0000-0002-1559-621XView further author information
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Akito Oizumib Nuclear Science Research Institute, Sector of Nuclear Science Research, Japan Atomic Energy Agency, IbarakiJapanORCID Iconhttps://orcid.org/0000-0002-7647-4005View further author information
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Kenji Nishiharab Nuclear Science Research Institute, Sector of Nuclear Science Research, Japan Atomic Energy Agency, IbarakiJapanORCID Iconhttps://orcid.org/0000-0003-3955-3756View further author information
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Masahiko Nakasea Laboratory for Zero-Carbon Energy, Institute of Innovative Research, Tokyo Institute of Technology, TokyoJapanView further author information
,
Asano Hidekazua Laboratory for Zero-Carbon Energy, Institute of Innovative Research, Tokyo Institute of Technology, TokyoJapanView further author information
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Kenji Takeshitaa Laboratory for Zero-Carbon Energy, Institute of Innovative Research, Tokyo Institute of Technology, TokyoJapanView further author information
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Pages 632-641 | Received 21 Sep 2021, Accepted 26 Sep 2022, Published online: 05 Nov 2022

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Tetsuo Fukasawa, Akihiro Suzuki, Yoichi Endo, Yaohiro Inagaki, Tatsumi Arima, Yusa Muroya, Keita Endo, Daisuke Watanabe, Tatsuro Matsumura, Katsunori Ishii & Junichi Yamashita. (2024) Flexible waste management system for the future application of MA P&T technology to the current high-level liquid waste. Journal of Nuclear Science and Technology 61:3, pages 307-317.
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Takumi Abe & Kenji Nishihara. (2023) Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations. Journal of Nuclear Science and Technology 0:0, pages 1-13.
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