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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
P. J. Ring, K. D. Challenger, H. J. Busboom
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 64-74
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31176
Articles are hosted by Taylor and Francis Online.
Burst rupture tests have been carried out on irradiated fuel pin cladding to determine the effect of intergranular attack on burst rupture strength and ductility and so to assess the ability of the weakened cladding to withstand power surge or loss of coolant conditions. The results from this series of tests indicate that the burst rupture strength or yield strength is not drastically reduced by localized attack extending through as much as 35% of the cladding thickness. Ductility values, however, do appear to be substantially reduced. In terms of reactor operation, this suggests that in a transient stress situation the cladding would be able to withstand higher stresses than previously predicted using a wall thinning criteria, based on the maximum depth of cladding attack, but would tolerate far less deformation than unattacked cladding before failure.