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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
J. D. Randall, J. V. Walker
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 69-73
Technical Paper | doi.org/10.13182/NSE61-A25987
Articles are hosted by Taylor and Francis Online.
A P0± calculation indicates that neutron detecting foils will cause no flux perturbation when prepared with a moderating ratio equal to that of the medium in which they are to be used. Such foils can be easily prepared from an appropriate solvent and solute. The activity in these foils can be conveniently determined on an absolute basis using liquid scintillation counting techniques, thus yielding an accurate value of absolute neutron flux. Measurements in polyethvlene are reported.
