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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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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.
S. K. Ho, F. J. Brechtel, T. Kenneth Fowler
Fusion Science and Technology | Volume 23 | Number 3 | May 1993 | Pages 321-330
Technical Paper | Safety/Environmental Aspect | doi.org/10.13182/FST93-A30160
Articles are hosted by Taylor and Francis Online.
A simplified scaling law approach for calculating activation-induced radioactive inventories is extended and applied. The goal is to provide a sufficiently accurate, very fast method to calculate activation radioactive inventories as an integral part of tokamak system design codes. The method is applied to a silicon carbide first wall, but now all relevant daughter nuclides are considered, and the results are used to calculate various indexes that can be used to characterize environmental and safety characteristics of fusion reactors. The indexes obtained from the scaling laws are in reasonable agreement with those derived from inventories calculated directly from more time-consuming Monte Carlo methods.