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
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.
Meeting Spotlight
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.”
Chris Keckler, Massimiliano Fratoni, Ehud Greenspan
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 1079-1088
Technical Paper | doi.org/10.1080/00295639.2020.1715688
Articles are hosted by Taylor and Francis Online.
This study quantifies the uncertainty in the calculated displacements per atom (DPA) value due to uncertainties in the neutron spectrum resulting from cross-section data uncertainty. Using generalized perturbation theory, covariance matrices, and fine-group DPA cross sections, a method for propagating nuclear data uncertainties through to the calculation of DPA is outlined. This method is then implemented for the case of a typical sodium-cooled breed-and-burn core. The majority of uncertainties in accumulated DPA were found to come from the inelastic scattering cross section for 238U. Overall the uncertainty in accumulated DPA is found to be roughly 2% of the total value.
