ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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.
Philippe Fougeras, Stéphane Cathalau, Jacques Mondot, Pavel Klenov
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 32-40
Technical Paper | doi.org/10.13182/NSE121-32
Articles are hosted by Taylor and Francis Online.
The EPICURE experimental program provides a complete and high-quality experimental database for evaluating the uncertainties in reactor physics calculations of plutonium-recycling pressurized water reactors. To understand possible discrepancies between experimental values and values calculated with the conventional scheme, a study is performed of the major physics approximations involved in the calculation of heterogeneous Mixed OXide-UO2-fueled cores. This study determines the origin of the significant discrepancies between the calculated and the measured power distributions. An optimized calculation scheme is developed based on the use of Sn transport calculations and on a refined energy group structure. Its application to the analysis of EPICURE experiments results in very satisfactory agreement.