Degradation mechanism of stainless steel by U-Zr-O molten mixture during core degradation of BWR severe accident

Author:

Itoh Ayumi1,Andrews Nathan C.2,Luxat David L.2,Gauntt Randall O.3,Kurata Masaki4,Kobayashi Yoshinao5

Affiliation:

1. Department of Materials Science and Engineering, Tokyo Institute of Technology, Meguro-ku, Tokyo, Japan

2. Sandia National Laboratories, Albuquerque, NM USA

3. Sandia National Laboratories, Albuquerque, NM, USA (Retired)

4. Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Japan Atomic Energy Agency, Ibaraki, Japan

5. Laboratory for Advanced Nuclear Engineering, Tokyo Institute of Technology, Tokyo, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference30 articles.

1. Tokyo Electric Power Company Holdings, Inc., Current status of fuel debris in Fukushima Daiichi nuclear power plants [WWW Document]. 2019. [cited 2020 Dec 9]. http://www.tepco.co.jp/decommission/progress/retrieval/index-j.html (in Japanese)

2. Tokyo Electric Power Company Holdings, Inc. Fukushima Daiichi Nuclear Power Station Unit 2 Primary Containment Vessel Internal Investigation Results [WWW Document]. 2018. [cited 2020 Dec 9]. http://www.tepco.co.jp/en/nu/fukushima-np/handouts/2018/images/handouts_180201_01-e.pdf

3. Main Findings, Remaining Uncertainties and Lessons Learned from the OECD/NEA BSAF Project

4. Confirmation of severe accident code modeling in light of the findings at Fukushima Daiichi NPPs

5. Gauntt RO, Humphries LL. Final results of the XR2-1 BWR metallic melt relocation experiment. No. NUREG/CR-6527; SAND-97-1039. Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; Sandia National Labs., Albuquerque, NM (United States); Science Applications International Corp., Albuquerque, NM (United States), 1997.

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