Axial Variations of Oxide Layer Growth and Hydrogen Uptake of BWR Fuel Claddings under Steam Starvation Conditions

Author:

Sakamoto Kan1ORCID,Adachi Mika2,Tokushima Kazuyuki2,Aomi Masaki2,Shibata Hiroki3,Nagae Yuji3ORCID,Kurata Masaki3

Affiliation:

1. Nippon Nuclear Fuel Development, 2163 Narita-cho, Oarai-machi, Ibaraki-ken 311-1313, JP

2. Global Nuclear Fuel–Japan, Co., Ltd., 3-1, Uchikawa 2-Chome, Yokosuka-Shi, Kanagawa-Ken 239-0836, JP

3. Japan Atomic Energy Agency, 790-1, Outsuka, Motooka, Tomioka-machi, Futaba-gun, Fukushima 979-1151, JP

Publisher

ASTM International

Reference15 articles.

1. Inter-Ministerial Council for Contaminated Water and Decommissioning Issues, “Mid- and Long-Term Roadmap towards the Decommissioning of TEPCO's Fukushima Daiichi Nuclear Power Station,” METI, 2019, https://web.archive.org/web/20220301192234/https://www.meti.go.jp/english/earthquake/nuclear/decommissioning/pdf/20191227_3.pdf

2. TEPCO, “The Development of and Lessons from the Fukushima Daiichi Nuclear Accident,” TEPCO, 2013, https://web.archive.org/web/20220309030816/https://www.tepco.co.jp/en/decommision/accident/images/outline01.pdf

3. Estimation of the Core Degradation and Relocation at the Fukushima Daiichi Nuclear Power Station Unit 2 Based on RELAP/SCDAPSIM Analysis;Madokoro;Nuclear Engineering and Design,2021

4. High Temperature Oxidation of Zircaloy-4 in Diluted Steam;Uetsuka;Journal of Nuclear Science and Technology,1989

5. System Code Evaluation of Near-Term Accident Tolerant Claddings during Boiling Water Reactor Short-Term and Long-Term Station Blackout Accidents;Wu;Nuclear Engineering and Design,2020

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