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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.”
G. Ferran, W. Haeck, M. Gonin
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 285-301
Technical Paper | doi.org/10.13182/NSE14-64
Articles are hosted by Taylor and Francis Online.
This paper describes in detail a new method to calculate the integral that appears in the expression of cross-section Doppler broadening. This method is based on a Fourier transform and seems quite promising as our tests suggest it is able to reach any required precision within a reasonable amount of calculation time. Another method to calculate Doppler-broadened cross sections based on Gauss quadrature will be presented, even if it requires too much computation time to be of practical use. Both methods have been implemented in a new nuclear data-processing software called GAIA, which is currently under development at the French Institut de Radioprotection et de Sûreté Nucléaire. Results of the comparison of the broadened cross sections obtained with the GAIA methods and with the NJOY processing system are discussed in the paper.