Corrosion resistance of titanium for nuclear waste container in non-oxidizing conditiou (III)

Wada, Ryutaro*; Nishimura, Tsutomu*; Shimogori, Kazutoshi*; Tomari, Haruo*; Masugata, Tsuyoshi*; Shimoda, Hideaki*

The corrosion-resistant material, titanium, is one of the candidate materials for nuclear fuel waste container. The purpose of this study is to investigate hydrogen embrittlement behavior of titanium in non-oxidizing solution clay estimated to be original condition of deep underground. The electrochemical tests were performed in deaerated carbonate solution at 50 $^{circ}$ C by 1440 hours, and hydrogen absorption behavior of titanium was investigated in with relation applied potential. The thoughts of hydrogen embrittlement and corrosion potential model of titanium were also discribed.

Language	:	Japanese
Report No.	:	JNC TJ8400 99-046
Pages	:	144 Pages
Publication Year/Month	:	1999/02
Patent information	:
PDF	:	JNC-TJ8400-99-046.pdf:14.01MB
Paper URL	:
Keywords	:	no keyword
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	神戸製鋼所
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Registration No. : GJ0820000069
JAEA Abstracts No. :

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