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Title: Stress corrosion of high-chromium nickel-base weld metals and AISI 316 nuclear grade stainless steel in simulated boiling water reactor environments

Journal Article · · Corrosion (Houston); (United States)
DOI:https://doi.org/10.5006/1.3583041· OSTI ID:6543803

The stress corrosion cracking (SCC) susceptibility of AlSl 316 NG (nuclear grade) stainless steel (SS), which has been welded with three high-chromium nickel-base weld metals (l-72, R-127, and R-135), was investigated by means of a series of slow strain rate tests (SSRTs) at a strain rate of 2 x 10/sup -7/ s/sup -1/. Tests were conducted in simulated boiling water reactor (BWR) environments at 288 C, which simulated either the normal BWR primary coolant chemistry or the impure (SO/sub 4//sup 2-/) chemistry that results from the intrusion of resin from the demineralizer system. The results indicated that all of the materials were immune to SCC in the normal BWR environment. In the resin intrusion environment, both the l-72 and R-135 weld metals were immune to SCC, but the R-127 material exhibited intergranular stress corrosion cracking. The AlSl 316 NG SS was susceptible to transgranular stress corrosion cracking in the resin intrusion environment, except when welded with l-72, in which case it was immune to SCC.

Research Organization:
Southwest Research Institute, 6220 Culebra Road, San Antonio, TX 78284
OSTI ID:
6543803
Journal Information:
Corrosion (Houston); (United States), Vol. 42:11
Country of Publication:
United States
Language:
English