Water corrosion resistance of ODS ferritic-martensitic steel tubes

被引:5
|
作者
Narita, Takeshi [1 ]
Ukai, Shigeharu [1 ]
Kaito, Takeji [1 ]
Ohtsuka, Satoshi [1 ]
Matsuda, Yasuji [2 ]
机构
[1] Japan Atom Energy Agcy, Oarai, Ibaraki 3111393, Japan
[2] Sumitomo Met Technol Inc, Amagasaki, Hyogo 6600856, Japan
关键词
F0800 (fusion reactor materials); C0500 (cladding materials); F0200 (fast reactor materials); S1000; (steels; ferritic/martensitic; low activation) spent fuel pool cooling system; water corrosion; pH; alkaline corrosion resistance; alloy elements;
D O I
10.3327/jnst.45.99
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A water corrosion test was conducted on oxide dispersion strengthened (ODS) steels in consideration of the spent fuel-pool cooling condition. The two types of ODS steel tubes tested were 9Cr-ODS and 12Cr-ODS. A test temperature of 333K was selected for the test by considering the environment of spent fuel-pool cooling system. The water corrosion test was performed for 1000h under a degassed and Cl-controlled water environment at pH values of 8.4, 10 and 12. The result demonstrated that at a pH value of 12, the weight losses of 9Cr- and 12Cr-ODS are larger than those of PNC-FMS and PNC316. The test specimens lose their metallic gloss and a slightly blackish surface is observed. It is considered that 9Cr-ODS and 12Cr-ODS claddings keep their strength and are comparable to that of conventional austenitic stainless steel and ferritic-martensitic stainless steel claddings in consideration of the spent-fuel-pool cooling condition.
引用
收藏
页码:99 / 102
页数:4
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