Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K-Reference-Cited by-同舟云学术

Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K

Published:2023-08-14 Issue: Volume: Page:1-11
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,Hagiwara Ryotaro²,Yasui Shintaro¹,Kobayashi Yoshinao¹,Sakamoto Kan³,Mizokami Masato⁴,Hirai Mutsumi⁴,Ito Kenichi⁴

Affiliation:

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

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

3. Nippon Nuclear Fuel Development Co. Ltd, Igaraki-gun, Ibaraki, Japan

4. Tokyo Electronic Power Company Holdings, Inc, Chiyoda-Ku, Tokyo, Japan

Funder

Tokyo Electronic Power Company Holdings

TEPCO Decommissioning Frontier Technology Creation Collaborative Research Base

Tokyo Institute of Technology

Nippon Nuclear Fuel Development Co. Ltd

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2023.2243947

Reference15 articles.

1. Current knowledge on core degradation phenomena, a review

2. Reaction Behavior of B4C Absorber Material with Stainless Steel and Zircaloy in Severe Light Water Reactor Accidents

3. Reactor Core Materials Interactions at Very High Temperatures

4. Phenomenology of BWR fuel assembly degradation

5. Hofmann P, Markiewicz M. Chemical interactions between as-received and pre-oxidized Zircaloy-4 and stainless steel at high temperatures (KfK5106). Kernforschungszentrum Karlsruhe; 1994.