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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
R. E. Kothmann, L. Green, M. D. Carelli, M. J. Manjoine, R. E. Wootton
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 551-557
Fusion Material and Plasma-Facing Component | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40215
Articles are hosted by Taylor and Francis Online.
Use of vanadium alloys is contemplated for the ITER blanket and guidance is needed to determine the extent of the data base for qualifying these alloys as structural material. A probabilistic methodology first employed in the fast breeder program is used to provide a preliminary assessment of the data base requirements. This methodology, which is applicable to any structural material, or in general to any design variable, determines the adequacy of the design by considering simultaneously all design affecting uncertainties, such as operational, nuclear, thermal-hydraulic, structural, geometric tolerances and material properties. In this study a thermal-mechanical calculational model of the ITER self cooled lithium blanket design was developed and the effect of design uncertainties on temperature (creep limited) and stress-strain (fatigue limited) were calculated. Based upon the current design, it was concluded that an uncertainty band of ± 30% on vanadium material properties is acceptable. Confirmatory irradiation data are however necessary.