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Chemical interactions between pre-oxidized Zircaloy-4 and 304 stainless steel-B4C melt at 1300 °C

  • Published:2018-09 Issue: Volume:508 Page:361-370
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Zheng LichunORCID,Hosoi Kazuya,Ueda Shigeru,Gao Xu,Kitamura Shin-ya,Kobayashi Yoshinao,Sudo Ayako

Funder

Accessibility for removal of fuel debris in BWR plant after severe accident

Nuclear S&T and Human Resource Development

Japan Science and Technology Agency

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference32 articles.

1. Reaction behavior of B4C absorber material with stainless steel and Zircaloy in severe light water reactor accidents;Hofmann;Nucl. Technol.,1990

2. Chemical Interactions between As-received and Pre-oxidized Zircaloy-4 and Stainless Steel at High Temperatures;Hofmann,1994

3. Reaction behavior between B4C, 304 grade of stainless steel and Zircaloy at 1473 K;Sasaki;J. Nucl. Mater.,2016

4. Interaction between B4C, 304 stainless steel, and Zircaloy-4 in H2O/H2 atmosphere at 1473 K;Gao;J. Nucl. Sci. Technol.,2018

5. Chemical interaction between VVER core components under accidental condition;Maróti;Nucl. Eng. Des.,1997
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