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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
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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.
Robert E. Canaan, Dale E. Klein
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 306-318
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35286
Articles are hosted by Taylor and Francis Online.
Natural convection heat transfer is experimentally investigated in an enclosed horizontal rod bundle, which characterizes a spent-fuel assembly during transport and some dry storage scenarios. The objective of this experimental study is to obtain convection correlations that can be used to easily incorporate convective effects into analytical models of horizontal spent-fuel systems and also to investigate the physical nature of natural convection in enclosed horizontal rod bundles in general. The resulting data consist of correlations of convective Nusselt number, which are defined in terms of the maximum and average assembly temperatures. The correlations have been corrected for radiation heat transfer using a numerical technique. The data suggest the presence of conduction and convection regimes, distinguished by a critical Rayleigh number. The correlation of the convection regime suggests turbulent flow conditions. Predictions of maximum assembly temperature using the presented correlations are compared with additional experimental data obtained in a horizontal enclosed rod bundle. Further comparisons are made with predictions from the widely used Wooten-Epstein equation and a recently developed theoretical approach based on an effective thermal conductivity model. Favorable results are obtained, especially for thermal conditions that favor natural convection, such as relatively low enclosure temperatures and abovestandard atmospheric pressure.