ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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.
Kune Yull Suh, Neil E. Todreas
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 229-240
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33877
Articles are hosted by Taylor and Francis Online.
An experimental study was carried out to quantitatively estimate the lateral drag changes due to flow structure alteration caused by the presence of wire-wrap spacers in liquid-metal fast breeder reactor rod assemblies. Specially designed test rod bundles were constructed employing vertical straight wires attached at various angles around the rods relative to the cross-flow direction. These bundles simulate the cross-flow pressure drop within a control volume with axial mesh size less than one-twelfth of wire-wrap lead length. The variables examined were wire angular positions, Reynolds number, and rod arrangements. The transverse pressure drop data for triangular-array rod bundles with wires have been correlated throughout the laminar and turbulent flow regimes. The correlation is in the form of a correction parameter to be applied to the friction factor-Reynolds number relationship for the corresponding bare rod bundle.
