IASCC crack growth rate of neutron irradiated low carbon austenitic stainless steels in simulated BWR condition

Chatani, Kazuhiro*; Takakura, Kenichi*; Ando, Masami*; Nakata, Kiyotomo*; Tanaka, Shigeaki*; Ishiyama, Yoshihide*; Hishida, Mamoru*; Kaji, Yoshiyuki

Crack growth rate (CGR) tests have been conducted with neutron irradiated compact tension (CT) specimens. The CGR tests of 316L and 304L base metals irradiated from 0.516 to 1.0710 $^{25}$ n/m $^{2}$ (E1MeV), and of 316L and 308L weld metals irradiated from 0.523 to 0.54110 $^{25}$ n/m $^{2}$ (E1MeV) were performed using the reversing dc potential drop (DCPD) method under constant load at a few average stress intensity factors (K) and electrochemical corrosion potential (ECP) conditions at 288 $^{circ}$ C in water. CGRs of base metals were increased with increasing neutron fluence. Clear reductions in CGRs of base metals and weld metals were measured with decreasing ECP levels.

Language	:	English
Journal	:	Proceedings of 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems (CD-ROM)
Volume	:
Number	:
Pages	:	9 Pages
Publication Year/Month	:	2007/00
Meeting title	:	13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems
Held date	:	2007/08
Location (city)	:	Whistler
Location (country)	:	Canada
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DOI for research data	:
Keywords	:	no keyword
Research Facility	:	JMTR(材料試験炉)
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	原子力安全基盤機構

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Registration No. : BB20071757
JAEA Abstracts No. : 36000611
Paper Submission No. : 3879

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