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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Deep geologic repository progress—2025 Update
Editor's note: This article has was originally published in November 2023. It has been updated with new information as of June 2025.
Outside my office, there is a display case filled with rock samples from all over the world. It contains a disk of translucent, orange salt from the Waste Isolation Pilot Plant near Carlsbad, N.M.; a core of white-and-bronze gneiss from the site of the future deep geologic repository in Eurajoki, Finland; several angular chunks of fine-grained, gray claystone from the underground research laboratory at Bure, France; and a piece of coarse-grained granite from the underground research tunnel in Daejeon, South Korea.
M. R. Fox, A. B. Hull, T. F. Kassner
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1619-1628
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29573
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Susceptibility of Types 316NG, 316, and 304 stainless steels (SS) to stress corrosion cracking was investigated in slow-strain-rate tests (SSRTs) in oxygenated water that simulates important parameters anticipated in first-wall/blanket systems. The water chemistry was based on a computer code that yielded the nominal concentrations of radiolytic species produced in an aqueous environment under conditions expected in the International Thermonuclear Experimental Reactor (ITER). Actual SSRTs were performed in a less benign, more oxidizing reference environment at temperatures of 52 to 150°C. Predominantly ductile fracture was observed in Type 316NG and nonsensitized Types 316 and 304 SS SSRT specimens that were strained to failure in a reference ITER water chemistry. The failure behavior of Type 304 SS specimens, heat-treated to yield sensitization values of 2, 3, and 20 Coulomb (C)/cm2 by the electrochemical potentiokinetic reactivation technique, demonstrated that the degree of sensitization dramatically affected susceptibility to intergranular stress corrosion cracking. Ranking for resistance to stress corrosion cracking in simulated ITER water by electron microscopy and SSRT parameters, i.e., failure time, ultimate strength, total elongation, and stress ratio, is 304 SS (EPR = 20<2 C/cm2)<316NG SS.