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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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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.
Chenglin Zhu, Yuhang Yan, Shuo Li, Hui Yu (SPICRI)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 732-737
The cosLATC is a multi-group two-dimensional lattice code developed by SNPSDC, which is an essential part in the COSINE(Core and System Integrated Engine) code package. Resonance self-shielding calculation is a very important part in the reactor physics calculation. It provides effective cross section for the next transport calculation. Traditional two-region resonance calculation method based on equivalence theory was developed in the cosLATC code. However, for the fuel pin which contains strong resonance self-shielding effect or huge absorption cross section nuclides, the spatial variation of the self-shielding effect is crucial to determine its radial power distribution. The equivalence theory assumes a spatially constant cross section within the fuel region and cannot evaluate spatially dependent resonance self-shielding effect. So the SDDM (Spatially Dependent Dancoff Method) self-shielding resonance was developed in the latest version of cosLATC which can split the fuel pellet into arbitrary number of annuli and generate the effective cross section for every annulus. A serial of benchmarks are calculated to verify this new resonance self-shielding module were performed. These benchmarks include different assembly problems of Watts Bar benchmark and critical benchmarks. The results show that the new resonance self-shielding module is capable of modeling the resonance self-shielding in a variety of PWR benchmarking cases, including difficult fuel lattice cases with poison, control rods or mixed gadolinia fuel rods. The critical calculation results can be accepted for the lattices which the conditions vary with the enrichment, radius of fuel rods, lattices pitch and experimental buckling.