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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
W. R. Martin, J. R. Weir
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 478-483
Technical Paper | doi.org/10.13182/NT65-A20559
Articles are hosted by Taylor and Francis Online.
The ductility of irradiated structural alloys is of concern in reactor design. The purpose of this study is to determine some of the parameters affecting such ductility. Type-304 stainless steel has been thus investigated up to 600°C. In general, the ductility of stainless steel, solution annealed prior to irradiation, is better than steel cold worked prior to irradiation. One exception to this generality occurs under the conditions of irradiation followed by straining at 200°C, where low ductility is observed for irradiated stainless steel, solution annealed prior to irradiation. Cold working followed by carbide precipitation at an intermediate temperature improves the ductility of irradiated stainless steel at 200°C.
