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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
G. J. Theus
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 388-397
Technical Paper | Reactor | doi.org/10.13182/NT76-A31521
Articles are hosted by Taylor and Francis Online.
High-temperature electrochemical tests have resulted in the stress corrosion cracking of Inconel-600 and Incoloy-800 (registered trademarks, International Nickel Company), and Type 304 stainless steel in caustic solutions. Results show that stress corrosion cracking of these alloys can be prevented or accelerated by varying their electrochemical potential. To a certain extent, the same effect can be achieved by altering the gas atmosphere above the test solution from a pure nitrogen cover gas to a mixture of 5% H2 and 95% N2. The effect of the cover gas can then be negated by adjusting the specimen’s electrochemical potential either to cause or to inhibit stress corrosion cracking. These types of experiments lead to a better determination of the boundary conditions within which stress corrosion cracking of the alloys occurs. Some specifics of the test results reveal that in deoxygenated caustic solutions, Inconel-600 cracks intergranularly at mildly anodic potentials; Incoloy-800 cracks transgranularly at reduced potentials (at or near the open circuit potential) and intergranularly at highly oxidizing potentials; and cracking is mixed (transgranular/intergranu-lar) for Type 304 stainless steel at or near the open circuit potential. The severity of cracking for both Inconel-600 and Incoloy-800 in deoxygenated caustic solutions is reduced by giving the materials a simulated post-weld heat treatment (1150°F for 18 h). Test results on Inconel-600 show that high-carbon (0.06%) material cracks less severely than low-carbon (0.02%) material, in both the simulated post-weld heat-treated condition and the mill-annealed condition. The results we obtained with the electrochemical corrosion techniques agree with results obtained using conventional corrosion methods for caustic stress corrosion cracking. Moreover, many metallurgical variables, which promote or retard caustic cracking, are the same as those conditions that promote or retard high-temperature high-purity water failures—particularly in the case of Inconel-600.