Localized corrosion behaviors of zircaloy in sea water containing solutions

Yamamoto, Masahiro ; Komatsu, Atsushi ; Motooka, Takafumi

As sea water was introduced into spent nuclear fuel pool (SFP) for emergency cooling of Fukushima Dai-ichi Nuclear Power Plant, it was wondered that corrosion problems of zircaloy as cladding materials. Then, corrosion behaviors of zircaloy-2 were examined. The results showed re-passivation potential and crevice potential were nobler than that of rest potential in the solution diluted 1/8 sea water and below 80 $^{circ}$ C. It means localized corrosion is inhibited in these conditions. Next we will examine the actual cladding materials for confirming the effect of oxide layer and hydride.

Language	:	Japanese
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Meeting title	:	材料と環境2012
Held date	:	2012/04
Location (city)	:	東京
Location (country)	:	日本
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Keywords	:	福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident
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Registration No. : BB20120078
JAEA Abstracts No. :
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