ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
Countering the nuclear workforce shortage narrative
James Chamberlain, director of the Nuclear, Utilities, and Energy Sector at Rullion, has declared that the nuclear industry will not have workforce challenges going forward. “It’s time to challenge the scarcity narrative,” he wrote in a recent online article. “Nuclear isn't short of talent; it’s short of imagination in how it attracts, trains, and supports the workforce of the future.”
N. E. Stauff, L. Buiron, B. Fontaine, G. Rimpault
Nuclear Technology | Volume 181 | Number 2 | February 2013 | Pages 241-250
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A15781
Articles are hosted by Taylor and Francis Online.
Sodium-cooled fast reactors (SFRs) remain the favorite candidate in France for a Generation IV (Gen IV) reactor fleet to be deployed within this century. Compared with earlier generations (Phénix, Superphénix, and European fast reactor), Gen IV SFRs require attractive economics together with enhanced safety and nonproliferation criteria. An innovative approach named Mathematical Estimation of Transients for Reactor design Orientation (METRO) has been developed with the objective of taking into account both SFR core economic performance and SFR transient incident behavior at an early stage of the core design process. Loss-of-flow, loss-of-heat-sink, and overpower transients are evaluated. Simplified modeling of transients has been developed and benchmarked against reference calculations with satisfactory results. The METRO approach to assessing the efficiency of design orientations is described in the following and applied to a carbide-fueled reactor core.