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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
Yasunori Kitamura, Yuta Eguchi
Nuclear Science and Engineering | Volume 178 | Number 3 | November 2014 | Pages 401-413
Technical Paper | doi.org/10.13182/NSE14-21
Articles are hosted by Taylor and Francis Online.
A series of integral reactor physics experiments conducted at the Very High Temperature Reactor Critical Assembly was analyzed to assemble it into a benchmark through an extensive peer-review process under the International Reactor Physics Experiment Evaluation Project. This benchmark provides the experimental data with respect to the criticalities of seven core configurations and the temperature effect on reactivity up to 200°C with explicit experimental uncertainties newly evaluated. It further presents the benchmark models and corresponding values with some simplifications so that it can be used by reactor designers for validating the analytical tools employed to design next-generation reactors and for establishing the safety basis for operation of these reactors.