Reaction behavior between B4C, 304 grade of stainless steel and Zircaloy at 1473 K

Ryosuke Sasaki, Shigeru Ueda, Sunjoong Kim, Xu Gao, Shinya Kitamura

Research output: Contribution to journalArticlepeer-review

12 Citations (Scopus)

Abstract

For a better understanding of the decommissioning of the Fukushima-daiichi nuclear power plant, the melting behavior of the control blade and the channel box should be clarified. In Fukushima nuclear reactor, the channel box was made of Zircaloy-4, and the control rode is made of B4C together with stainless steel cladding and sheath. In the study, the interaction among B4C, stainless steel (SUS), and Zircaloy-4 was investigated at 1473 K in either argon or air atmosphere. In argon, Zircaloy is melted by the diffusion of elements from SUS, and SUS was melted at 1473 K by the diffusion of C and B. In air, SUS reacted with B2O3 and formed an oxides melt firstly. Then, the oxidized Zircaloy contacted with this melt and fused. Moreover, the progress of core melting process during severe accident under different atmospheres was firstly discussed.

Original languageEnglish
Pages (from-to)205-214
Number of pages10
JournalJournal of Nuclear Materials
Volume477
DOIs
Publication statusPublished - 2016 Aug 15

Keywords

  • 304 grade stainless steel
  • BC
  • BO
  • Control blade
  • Melting behavior
  • Oxidation
  • Steam
  • Zircaloy

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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