Influence of Zn injection on PWSCC crack growth rates of alloy 600 under simulated primary coolant environments of pressurized water reactor

Chimi, Yasuhiro; Sato, Kenji*; Kasahara, Shigeki; Umehara, Ryuji*; Hata, Kuniki ; Hanawa, Satoshi ; Nishiyama, Yutaka

To investigate the influence of Zinc (Zn) injection on primary water stress corrosion cracking (PWSCC) growth behavior, crack growth tests of 10% cold-worked Alloy 600 in simulated primary water environment of pressurized water reactor (PWR) at 320 $^{circ}$ C and 360 $^{circ}$ C, with and without Zn injection, under dissolved hydrogen (DH) conditions of 5, 30, and 50 cc/kgH $_{2}$ O. As a result of the crack growth tests at 360 $^{circ}$ C, it is implied that Zn injection suppresses the oxidation inside the crack and the crack growth rate (CGR). From the crack growth tests at 320 $^{circ}$ C with Zn injection, DH-dependence of CGR showed a similar tendency to the predicted CGR based on the CGR data without Zn injection. Obvious influence of Zn injection on DH-dependence of CGR at 320 $^{circ}$ C was not observed in the present study.

Language	:	English
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Meeting title	:	Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia 2017 (AWC 2017) & 5th International Symposium on Materials and Reliability in Nuclear Power Plants (5th MRNPP)
Held date	:	2017/09
Location (city)	:	Shenyang
Location (country)	:	China
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Keywords	:	PWSCC; Crack Growth Rate; Alloy 600; Zn Injection; PWR; Primary Coolant Environment; Dissolved Hydrogen
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Cooperating Institute	:	原子力規制委員会原子力規制庁

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Registration No. : BB20171192
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