Grain Boundary Composition and Irradiation-Assisted Stress Corrosion Cracking Resistance in Type 348 Stainless Steel
Source abstract
Abstract
Scanning transmission electron microscopy (STEM) analyses, in-reactor swelling mandrel tests, and laboratory constant extension rate tensile (CERT) tests were conducted on nine custom type 348 (UNS S34800) stainless steel (SS) alloys in an attempt to correlate grain boundary composition with irradiation-assisted stress corrosion cracking (IASCC) resistance. Phosphorus (P) enrichment showed the best correlation with in-reactor test results, and chromium (Cr) depletion showed the best correlation with laboratory results. Silicon (Si) and P enrichment were found to depend quantitatively on the bulk concentrations of these elements. The amount of Cr depletion seemed dependent at least partially on the amounts of Si and/or P enrichment. Si and P enrichment and Cr depletion were suppressed by higher carbon (C) contents, such as that present in commercial-purity type 348 SS.
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Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
Affiliations
*General Electric Nuclear Energy, 175 Curtner Ave., San Jose, CA, 95125.
**Hitachi Ltd., Hitachi Research Laboratory, Hitachi-shi 317, Japan.
***Toshiba Corp., Isogo Nuclear Engineering Center, Yokohama 235, Japan.
****Tokyo Electric Power Co., Tokyo 100, Japan.
References (10)
Show source-provided references
1. The Correlation of Grain Boundary Composition on Irradiated Stainless Steel with IASCC Resistance
2. Influence of Grain Boundary Composition on the IASCC Susceptibility of Type 348 Stainless Steel
3. High-Temperature Solution Annealing As an IASCC Mitigation Technique
4. Changes in Grain Boundary Composition Induced by Neutron Irradiation on Austenitic Stainless Steels
5. Effects of Fluence and Dissolved Oxygen on IASCC in Austenitic Stainless Steels
6. Irradiation-Induced Sensitization and Stress Corrosion Cracking of Type 304 Stainless Steel Core-Internal Components
7. Irradiation-Assisted Stress Corrosion Cracking and Grain Boundary Segregation in Heat-Treated Type 304 SS10.1520/STP24658S ↗
8. The Relationship of Grain Boundary Composition in Irradiated Type 304 SS to Neutron Fluence and IASCC
9. The Effects of Minor Elements on IASCC Susceptibility in Austenitic Stainless Steels Irradiated with Neutrons
10. Jacobs · Corrosion · 1990 · 46 · 3010.5006/1.3585063 ↗