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
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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.
David J. Loaiza, Rene Sanchez, Roger Brewer
Nuclear Science and Engineering | Volume 143 | Number 2 | February 2003 | Pages 132-140
Technical Paper | doi.org/10.13182/NSE03-A2324
Articles are hosted by Taylor and Francis Online.
Critical experiments are carried out in order to validate, improve, and benchmark the extensive data calculations available. A series of such experiments was performed at the Los Alamos Criticality Experiments Facility. These experiments were performed to provide criticality safety data for waste matrix materials. These critical experiments were fueled with highly enriched uranium, moderated and reflected with polyethylene, and mixed with silicon dioxide (SiO2), aluminum (Al), magnesium oxide (MgO), and gadolinium (Gd). The uncertainties affecting the experiment were divided into three broad categories: mass measurement, geometry, and material composition. Each category is considered in turn, and then the total experimental uncertainty is derived. All four experiments had a measured keff of 1.001. The sensitivity analyses of these critical experiments yielded uncertainties in the measured keff of ±0.0026 for SiO2, ±0.0026 for Al, ±0.0021 for MgO, and ±0.0029 for Gd. These experiments were judged to be of benchmark quality.