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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
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
T. V. Kulsartov, Zh. A. Zaurbekova, Y. A. Kenzhin, A. Shaimerdenov, E. Nesterov
Fusion Science and Technology | Volume 76 | Number 5 | July 2020 | Pages 632-641
Technical Paper | doi.org/10.1080/15361055.2020.1740557
Articles are hosted by Taylor and Francis Online.
The paper analyzes the results of reactor studies on tritium generation and release from the lead-lithium eutectic PbLi in conditions of reactor irradiation. In this paper, the initial stage of eutectic irradiation is considered. The dependences of tritium and helium release at a reactor power of 1 MW and the following eutectic temperatures were considered: 573, 673, and 773 K. Using an integrated model based on solving related systems of equations, including heat transfer equations, convective mass transfer equations, and diffusion equations, equilibrium temperature distributions over the eutectic were calculated. The evolution (time variation) of tritium concentration distributions in the volume of the eutectic and in traps at different temperatures of the eutectic is calculated.