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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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Nuclear Technology
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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.
Paul Sasa, August W. Cronenberg+, Michael G. Stevenson
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 233-250
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32470
Articles are hosted by Taylor and Francis Online.
One aspect of nuclear reactor safety assessment is a prediction of fuel behavior associated with postulated overheating events, which includes an assessment of the role of fission product inventory, contained within irradiated fuel elements, on fuel relocation potential. In general, the gaseous fission products, such as xenon and krypton, have been considered the most likely candidates for fuel relocation. However, the fissioning of UO2 fuel in both a fast and slow neutron spectrum also results in the generation of a significant quantity of such metallic fission products as barium, palladium, molybdenum, and other metal species. Metallurgical analysis of irradiated fuel indicates that such metals aggregate into inclusions found throughout the fuel matrix. During normal reactor operation, such metallic inclusions are in a solid state, but at the elevated temperatures expected for overheating accident transients, such inclusions may tend to volatilize, contributing to fuel motion. This paper involves an assessment of effect of such metallic fission product inclusions on fuel motion potential for accident analysis and is the first known attempt at such an assessment. To assess this potential, two limiting calculational assessments were made. Results indicate that if the inclusion constituents are assumed to be segregated elementally, then the presence of the highly volatile species such as antimony, palladium, and iron can result in an estimated 30% expansion just prior to fuel vaporization. However, under the more probable assumption of complete miscibility of constituents, the effect of metallic inclusion vaporization would be of little consequence to fuel motion.