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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
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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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
H. O. Menlove, R. A. Forster, D. L. Matthews
Nuclear Technology | Volume 19 | Number 3 | September 1973 | Pages 181-187
Technical Paper | Analysis | doi.org/10.13182/NT73-A15880
Articles are hosted by Taylor and Francis Online.
An 124Sb-Be(γ,n) assay system has been designed and fabricated for the measurement of fissile content in small samples, fuel rods, and solutions. The instrument uses multiple 4He gas tube detectors to count fast neutrons induced in the assay sample by the 124Sb-Be source neutrons. The 4He detectors are biased to count only neutrons with energies above the 26- and 360-keV source neutrons. Computer calculations were used to optimize the design of the irradiation unit, giving a factor of ∼3 improvement in the induced fission rate. The assay unit has been applied to the measurement of small UO2 samples, pressurized water and boiling water reactor fuel rods, and high temperature gas-cooled reactor fuel.
