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Report No.

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 1.07$$times$$10$$^{25}$$n/m$$^{2}$$ (E$$>$$1MeV), and of 316L and 308L weld metals irradiated from 0.523 to 0.541$$times$$10$$^{25}$$n/m$$^{2}$$ (E$$>$$1MeV) 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.



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