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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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February 2025
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Latest News
State lawmakers across the country push for more nuclear
From lifting moratoriums to launching studies to labeling it as clean, state lawmakers are exploring ways to give nuclear energy a boost in 2025. Here’s a look at some of the pronuclear legislation under review.
Muhammad Altahhan, Sandesh Bhaskar, Paolo Balestra, Jason Hou, Maria Avramova (NCSU), Nicholas Smith (Southern Co.)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 1248-1256
In this study, a hybrid two-dimensional (2D) / three-dimensional (3D) Liquid Fuel Molten Salt Reactor (LFMSR) core is modelled using the Multi-physics C++ code GeN-Foam (General Nuclear Foam). GeNFoam has three main sub-solvers - for neutron kinetics, thermal hydraulics, and thermal mechanics. A steady state analysis of a simplified 2D LFMSR model has been performed assuming rotational symmetry to cross validate the code with the commercial ANSYS Computational Fluid Dynamics (CFD) code Fluent. The calculations showed a very good agreement between the two codes allowing moving onto a 3D model simulation. A coupled 3D neutron kinetic and CFD steady state analysis of the 3D LFMSR core has been performed modeling one quarter of the core using the core symmetry to reduce the computational time. The GeN-Foam neutron kinetics sub-solver has been designed to consider also the drifting of the delayed neutrons precursors in LFMSR, a capability not yet implemented in the most of current neutron kinetics codes. The mixed Uranium and Plutonium chloride fuel has been selected in this preliminary study. The calculation results meet the expectations showing that GeN-Foam has all the features necessary for LFMSR design modeling and simulation. The delayed neutrons precursors behavior is as expected - the longer-lived isotopes accumulate near the outlet while the short-lived ones lay at the generation location. The calculated maximum temperature is close to the expected one and the velocity profile is consistent with a low viscosity, high density fluid velocity profile.