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
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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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.
D. Ginestar, G. Verdú, J. March-Leuba
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 172-180
Technical Paper | doi.org/10.13182/NSE02-A2253
Articles are hosted by Taylor and Francis Online.
There is currently much interest in developing new codes and improving the existing ones to be able to predict instabilities of nuclear power reactors. Stability calculations are very sensitive to the models used for the reactor and the numerical methods used to integrate them. To clarify this dependence, a simplified thermohydraulic model has been proposed, and several numerical schemes have been used to integrate the model. A numerical example has been analyzed showing that the behavior of the solution depends mainly on the spatial discretization used.