ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
R. H. Augustson, C. N. Henry, C. R. Weisbin
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 197-199
Technical Note | Analysis | doi.org/10.13182/NT72-A31136
Articles are hosted by Taylor and Francis Online.
The 235U content of a spent MTR fuel element enclosed in a lead transfer cask has been nondestructively measured by observing the delayed-neutron emissions following high energy neutron induced fission. Fourteen MeV neutrons from a (D,T) neutron generator moderated through 8 in. of lead were used as the interrogating radiation. A DTF-IV calculation was used to correct the data for the contributions due to other fissionable isotopes. The nondestructive measurement agreed to within 1.5% with the 235U content as predicted by reactor burnup calculations.
