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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
Yoshiro Nishioka, Satoru Kuboya, Yuya Takahashi, Hideki Horie, Mika Tahara (Toshiba Energy Systems & Solutions Corp), Tadashi Fujii (Hitachi-GE Nuclear Energy, Ltd), Takafumi Tsuji (Chubu Electric Power Co., Inc.)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 223-228
The passive debris cooling system provides a means to stably hold and cool the molten core (debris) dropped from the reactor vessel by the heat resistant material laid on the bottom of the containment vessel. As a heat resistant material, high melting point and highly corrosion-resistant oxide is laid on the pedestal and water is injected afterwards to suppress MCCI by the molten core. In the past research, although knowledge about molten core and concrete has been acquired, knowledge about interaction between molten core and heat resistant material is insufficient. Therefore, element tests on heat resistant materials were conducted, various heat resistant materials were screened, and molten core - heat resistant material interaction model was constructed using the obtained findings. Using the constructed model, we evaluated the erosion / heat transfer behavior of the heat resistant material assuming the bottom of the BWR / Mark - II type containment vessel at the time of severe accident and confirmed the MCCI suppression effect by the passive debris cooling system.