Both Alloys 600 and 690 were studied to understand the effect of heat
treatment on the sensitization and SCC behavior of these alloys. The m
icrostructural evolution and chromium depletion near the grain boundar
ies were carefully studied using analytical electron microscopy. The m
ajority of the precipitates formed in Alloy 600 was found to be M(7)C(
3) with a hexagonal structure (a(0) = 1.398 nm, c(0) = 0.45 nm); where
as the carbides found in Alloy 690 were identified as M(23)C(6) with a
n fcc structure (a(0) = 1.06 nm). Modified Huey test performed in boil
ing 40% HNO3 was used to study the effect of heat treatment and degree
of sensitization. Constant load tests and constant extension rate tes
ts were performed in the solution containing sodium thiosulfate to stu
dy the SCC resistance of these alloys. The results of the constant loa
d tests for Alloy 600 indicated that the susceptibility to SCC is sens
itive to the chromium depletion depth at grain boundary, and the minim
um value to prevent SCC failure is approximately 8 wt%. No SCC was obs
erved for Alloy 690 tested using constand load and CERT in the same en
vironments. All tests showed that Alloy 690 has a far better resistanc
e to intergranular attack and SCC than Alloy 600, which is believed du
e to its high chromium content. It is therefore anticipated that Alloy
690 now a better substitute to Alloy 600 as a steam generator tubing
material for pressurized water reactor will also offer a superior corr
osion resistance when ''sensitized'' and in particular if exposed to s
ulfur containing media such as thiosulfate solutions.