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
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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.
J. B. Conway, J. T. Berling, R. H. Stentz
Nuclear Technology | Volume 9 | Number 1 | July 1970 | Pages 31-39
Fuel Cladding Model | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28725
Articles are hosted by Taylor and Francis Online.
Short-term tensile data have been generated using a new experimental technique which allows the true total axial strain rate to be maintained constant all the way to fracture. Tensile data at 650°C (1200°F) for irradiated and unirradiated specimens of AISI 304 and 316 stainless steel are presented and compared. A new relationship between low-cycle fatigue and short-term tensile behavior is discussed and applied to data for irradiated and unirradiated material. The effectiveness of this approach is shown to be excellent. This method should allow the low-cycle fatigue behavior for irradiated material to be estimated with acceptable accuracy. Hold times at peak strain have a noticeable effect on fatigue behavior as evidenced in tests at 650°C. These effects are most pronounced when hold periods are employed in only the tension portion of the cycle. An interesting correlation of hold-time data is presented, based on a logarithmic plot of time to fracture vs the length of the hold period. Another important correlation involves a relationship which identifies a method for estimating hold-time effects from a knowledge of the effect of strain rate on low-cycle fatigue behavior.