ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
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.
P. Hurst, H. C. Cowen
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 449-459
Technical Paper | Materials | doi.org/10.13182/NT55-449
Articles are hosted by Taylor and Francis Online.
Stress corrosion studies in caustic environments have been carried out on the ferritic 2 1/4 Cr—Mo steel, with particular reference to its use in the evaporators of the U.K. prototype fast reactor. The quench-hard-ened steel has been found to be susceptible to stress corrosion cracking (SCC) throughout the temperature range of 50 to 300°C. In 30% caustic soda at 116°C, this susceptibility extends over the potential range −900 to +100 mV (Hg/HgO). On tempering, SCC occurs at −900 to −700 mV, but only at more positive potentials when preceded by an overheating treatment. Mechanisms by which cracking occurs under the different conditions studied are discussed. Cracking can occur in hard tube-to-tube-plate welds exposed to caustic environments as a consequence of fabrication stresses, but it has been shown that this can be avoided by shot-peening.