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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
J. A. Vitti, P. K. Doherty, G. F. di Lauro, J. C. Gilbertson, D. W. Stuteville
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 442-451
Technical Paper | Fuel | doi.org/10.13182/NT75-A24444
Articles are hosted by Taylor and Francis Online.
A preliminary assessment of proof testing 13 prototypical liquid-metal fast breeder reactor (LMFBR) carbide fuel assemblies in fast test reactor (FTR) driver positions leads to the conclusion that the testing plan is practical and should produce a large amount of data at operating conditions very similar to those that would be found in large commercial carbide-fueled LMFBR s. Three subassembly configurations were designed, each capable of being directly substituted into FTR driver positions and made compatible with the FTR geometry, fuel handling, power, temperature, subassembly flow rates, and pin-bundle pressure drop. Two sodium-bonded designs, one with 91 fuel pins with a 0.370-in. o.d. and the other with 127 fuel pins with a 0.315-in. o.d. per subassembly were established. Calculated peak linear power and peak discharge burnup slightly exceed present commercial design objectives of 30 kW/ft and 73 MWd/kg. Individual assembly power history, flux, and enrichments are represented quite well in the FTR for commercial outer-zone fuel assemblies. Inner-zone operating conditions, however, are not simulated as closely. Impact effects of the proof-test assemblies on FTR operation are judged to be manageable.