Estimation of long-term ex-vessel debris cooling behavior in Fukushima Daiichi Nuclear Power Plant unit 3
Author:
Affiliation:
1. Japan Atomic Energy Agency
2. Cooperative Major in Nuclear Energy, Waseda University
Publisher
Japan Society of Mechanical Engineers
Subject
General Medicine
Link
https://www.jstage.jst.go.jp/article/mej/9/2/9_21-00436/_pdf
Reference16 articles.
1. Nuclear Regulation Authority, Interim report on research and analysis of Fukushima-Daiichi Nuclear Power Plant accident (draft version) (in Japanese), available from < https://www.nsr.go.jp/data/000345038.pdf#page=216 > (accessed on 17 December, 2021).
2. Sato, I., An interpretation of Fukushima-Daiichi Unit 3 plant data covering the two-week accident progression phase based on correction for pressure data, J. Nuclear Science and Technology, Vol.56, Issue 5 (2019), pp394-411.
3. Sato, I., Arai, Y. and Yoshikawa, S., Evaluation of core material energy change during the in-vessel phase of Fukushima-Daiichi Unit 3 based on observed pressure data utilizing GOTHIC code analysis, J. of Nuclear Science and Technology, Vol.54, Issue 8 (2021a)
4. Sato, Analysis of Fukushima-Daiichi Nuclear Power Plant Unit 3 pressure data and obtained insights on accident progression behavior, Nuclear Engineering and Design, Vol. 383 (2021b).
5. TEPCO, Approximated Water Injection Amount for Units 1 to 3 (In Japanese) (2011a), available from < https://www4.tepco.co.jp/decommission/data/past_data/accident_plantdata/pdf/f1_7_Sousajisseki_20110717.pdf > (accessed on 17 December, 2021).
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1. MAAP code analysis for the in-vessel phase of Fukushima-Daiichi Nuclear Power Station Unit 1 and comparison of the results among Units 1 to 3;Nuclear Engineering and Design;2024-06
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