Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 2-Reference-Cited by-同舟云学术

Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 2

Published:2024-05-13 Issue: Volume: Page:1-17
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Itoh Ayumi¹,Inoue Kosuke²,Kobayashi Yoshinao¹,Sakamoto Kan³,Endo Yoichi³,Nozaki Kenichiro⁴,Chai Penghui⁴,Suehiro Shoichi⁴,Honda Takeshi⁵,Owada Kenji⁵,Mizokami Masato⁵,Hirai Mutsumi⁵,Ito Kenichi⁵,Mizokami Shinya⁵

Affiliation:

1. Laboratory for Zero-Carbon Energy, Tokyo Institute of Technology, Tokyo, Japan

2. Department of Materials Science and Engineering, Tokyo Institute of Technology, Tokyo, Japan

3. Research Department, Nippon Nuclear Fuel Development Co. Ltd, Oarai-machi, Japan

4. Nuclear Core Engineering Department, TEPCO SYSTEMS CORPORATION, Tokyo, Japan

5. Fukushima Daiichi Decontamination and Decommissioning Engineering Company, Tokyo Electric Power Company Holdings, Inc, Tokyo, Japan

Funder

Tokyo Electronic Power Company Holdings

Publisher

Informa UK Limited

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2024.2350534

Reference20 articles.

1. Tokyo Electric Power Company Holdings Inc. Fukushima Daiichi nuclear power station unit 2 primary containment vessel internal investigation [internet]. 2018. Available from: https://www.tepco.co.jp/en/nu/fukushima-np/handouts/2018/images/handouts_180426_02-e.pdf

2. Synopsis and outcome of the QUENCH experimental program

3. Tokyo Electric Power Company Holdings Inc. Examination into the reactor pressure increase after forced depressurization at unit-2 using a Thermal-Hydraulic Code (attachment 2-9) [Internet]. 2017. Available from: https://www4.tepco.co.jp/en/press/corp-com/release/betu17_e/images/171225e0227.pdf

4. EXPERIMENTAL STUDY OF STAINLESS STEEL 304L INTERACTION WITH ZIRCALOY AT HIGH TEMPERATURES

5. Effect of Isothermal Hold on the Microstructural Evolution of the Stainless Steel 304L/Zircaloy-4 Interface