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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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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.”
Xinwu Su, Zhengjun Zhang, Yinlu Han
Nuclear Science and Engineering | Volume 181 | Number 3 | November 2015 | Pages 272-288
Technical Paper | doi.org/10.13182/NSE15-1
Articles are hosted by Taylor and Francis Online.
All cross sections of neutron-induced reactions, angular distributions, energy spectra, and double-differential cross sections for n + 113,115,nat.In reactions are consistently calculated and analyzed at incident neutron energies below 200 MeV by using nuclear theoretical models. The isomeric cross section is especially calculated. The theoretical results are further compared with the available experimental data and the evaluated results in ENDF/B-VII, JENDL-4, and TENDL-2012.