Effects of water and irradiation temperatures on IASCC susceptibility of type 316 stainless steel

Current Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy

“…On the other hand, it has been indicated that irradiation hardening often increases the susceptibility to IASCC of austenitic stainless steel. 47) Slow strain rate test (SSRT) in high-temperature water environments was carried out for irradiated F82H specimens to 2 dpa in JMTR at 523 K. Almost no indication of environmentally assisted cracking was detected.…”

Candidate Materials Evaluation for Supercritical Water-Cooled Reactor

“…Based on the results of Caudron et al [12], who observed YFeO 3 in yttrium-ion-implanted iron, and Przybylski et al [13], who observed that YCrO 3 was formed in yttrium-implanted Co-45Cr, it is speculated that the phase formed in the yttrium-containing oxide may be YMO 3 (M: Fe or/and Cr). Thermodynamic data for the formation of YFeO 3 in a Fe-Y-O system at elevated temperatures were studied by Piekarczyk et al [14]. The results indicated that the formation of YFeO 3 from metallic iron, yttrium oxide and oxygen is thermodynamically possible, especially in environments at relatively low temperatures and low oxygen content.…”

“…The difference in oxide microstructure mainly results from the grain size effect on Cr flux, since Cr has the highest diffusion coefficient in this system [154]. Based on the equations of Cr flux via lattice and GBs for a semi-infinite geometry, assuming negligible transfer to and from the grain [155,156], (14) (15)the flux ratio of Cr will be: (16) where d is grain size; w is grain boundary width, which is usually about 0.5 nm [157], D L and D B are the lattice and grain boundary diffusion coefficients C B and C 1 are the bulk concentration and fixed surface concentration; and t is the period of oxidation. Since Incoloy alloy 800 has the same chemical composition as alloy 800H, the diffusion coefficients of Cr via lattice and GBs in Incoloy alloy 800 are [158]: 17) (18and should be applicable for alloy 800H.…”

SCC behavior of solid-HIPed and irradiated type 316LN-IG stainless steel in oxygenated or hydrogenated water at 423–603K

“…Authors reported in previous works [16,17] that with SSs irradiated below 573 K, IASCC did not occur during a slow strain rate testing (SSRT) below 513 K in oxygenated water. In hydrogenated water from 561 to 593 K, IASCC was suppressed for austenitic SSs irradiated below $4 dpa [12,13].…”

“…In such service conditions, austenitic stainless steels become susceptible to irradiation assisted stress corrosion cracking (IASCC). Stress corrosion cracking (SCC) of unirradiated materials as well as IASCC is affected by environmental conditions such as water chemistry and temperature [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15][16][17].…”