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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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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Donald L. Smith
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 109-114
Technical Note | doi.org/10.13182/NSE79-A21294
Articles are hosted by Taylor and Francis Online.
Cross-section ratios for production of 0.843-, 1.013-, and 2.209-MeV gamma rays at 55 deg by the 27Al(n,n′γ)27Al reaction relative to fast-neutron fission of 235U have been measured at intervals of ∼0.05 MeV from threshold up to ∼2.5 MeV, with an average neutron energy resolution of ∼0.08 MeV. These ratios and ENDF/B-IV fission cross sections were used to compute gamma-ray production cross sections. Gamma-ray angular distributions were measured at En = 1.112, 1.310, 1.512, 1.714, 1.914, 2.118, 2.310, and 2.512 MeV. These distributions were found to be isotropic within the experimental errors. The experimental results are compared with data from the literature and with results from optical/statistical model calculations of neutron inelastic scattering from aluminum.
