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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
Zhiyao Xing, Eugene Shwageraus (Univ of Cambridge)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 777-786
Prismatic block type Fluoride-salt-cooled High-temperature Reactors (FHRs) can benefit from Advanced Gas-cooled Reactor (AGR) technologies. To provide guidance for future AGR-like FHR design, this paper, based on systematic searches across a wide range of AGR-like assembly models and simplified single pin models, studies the beginning of cycle excess reactivity and coolant temperature coefficients of FHRs with different design parameters and alternative salt coolants. LiF-NaF-KF (FLiNaK) and non-Tritium-producing salt NaF-ZrF4 are studied as coolant options alternative to 2LiF-BeF2 (FLiBe) using unit cell models. The results suggest that the NaF-ZrF4 cooled, UC fuelled single pin models with 40% to 100% salt to graphite mass ratios and pitch to diameter ratios of 4.0 to 4.8 can achieve the best beginning of cycle neutronics performances among all designs options surveyed. While the assembly models and pin cell models capture the same reactor physics phenomena, designing FHR strictly within the physical constraint of AGR configuration limits the designs space and results in poorer neutronics performance comparing with the best performing unit cell models. Greater degrees of freedom could be considered in the future assembly level design process to best capture the desirable neutronics benefits of the recommended single pin designs.