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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.
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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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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.
K. Koebke, H. Haase, L. Hetzelt, H.-J. Winter
Nuclear Science and Engineering | Volume 92 | Number 1 | January 1986 | Pages 56-65
Technical Paper | doi.org/10.13182/NSE86-A17865
Articles are hosted by Taylor and Francis Online.
The efficient use of nodal methods for three-dimensional two-group reactor calculations requires homogenization over large volumes or nodes. This homogenization removes the internal structure of the nodes. On the other hand, accurate pinwise power distributions are indispensable for light water reactor design. A homogenization and dehomogenization procedure called the simplified equivalence theory (SET) has been proposed, which allows the accurate and inexpensive determination of pinwise power distributions of fresh reactor cores. The SET procedure is extended to burnup and parameter dependencies. For the case of fuel assembly homogenization and dehomogenization, this extension is validated by a procedure that allows assessment of the accuracy of the method, referring exclusively to the spectral geometry of the assembly. For the validation of the equivalent reflector model, a nodal reactor test problem is set up which shows that this model is adequate to describe core/reflector interactions under burnup conditions.