Structural Integrity Assessment of WWER Internals on Stress Corrosion Cracking Criterion
Keyword(s):
Stress-damage dose curve (SDDC) is introduced on the basis of the analysis of experimental data on susceptibility to intergranular stress corrosion cracking (IGSCC) of irradiated stainless steels (SS). Approaches to determination of the SDDC parameters are considered. Based on SDDC calculative procedure for estimation of reactor vessel internals (RVI) lifetime by criterion of initiation crack due to IGSCC is proposed.
2001 ◽
Vol 38
(3)
◽
pp. 183-192
◽
2000 ◽
Vol 37
(10)
◽
pp. 901-912
◽
1993 ◽
pp. 126-129
◽
2008 ◽
pp. 123-141
◽