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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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
F. Roelofs, D. Dovizio, D. Visser, K. Zwijsen, A. Shams (NRG)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 109-116
European lead fast reactor designs are all pool-type designs. The pool basically forms the primary system of the reactor and as such plays a crucial role in the design and safety analyses of such reactors. The safety analyses require thorough understanding of the flow and heat transport in the primary system. In the past, the design and safety analysis of liquid metal cooled reactors highly relied on design specific experimental set-ups using either a transparent, easy-to-handle simulant fluid relying on scaling analyses or using liquid metals while coping with measurement limitations. Nowadays, Computational Fluid Dynamics (CFD) has become an integral tool of the advanced reactor designer allowing simulations in 3 dimensions. However, in a heavy liquid metal pool, many complex physical phenomena come together. As such, these simulations need separate validation of the capabilities of the applied CFD codes and, on top of that, integral validation using large scale experimental facilities. This paper discusses the ongoing efforts at NRG in the Netherlands on validation of CFD tools for heavy liquid metal pool simulations with respect to flow and heat transport.