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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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BREAKING NEWS: Trump issues executive orders to overhaul nuclear industry
The Trump administration issued four executive orders today aimed at boosting domestic nuclear deployment ahead of significant growth in projected energy demand in the coming decades.
During a live signing in the Oval Office, President Donald Trump called nuclear “a hot industry,” adding, “It’s a brilliant industry. [But] you’ve got to do it right. It’s become very safe and environmental.”
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.