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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
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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.”
Mukesh Tayal, Lorne D. Macdonald, Erl Kohn, Walter P. Dovigo
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 300-313
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT89-A34252
Articles are hosted by Taylor and Francis Online.
The GASOUT computer code calculates fission gas release, activity release, and fission product swelling in a Canada deuterium uranium (CANDU) fuel element during transient (nonequilibrium) conditions such as load following, postulated accidents involving high temperatures, and temporary postdryout operation of fuel. The phenomena modeled in the code include production of isotopes; diffusion; grain growth, both equiaxed and columnar; sweeping by grain boundaries; growth of grain-boundary bubbles; interlinkage of bubbles; grain-face separation; release by melting; radioactive decay; and effect of precursors. These phenomena are described in the code by rate equations, which are integrated numerically within the code. Therefore, the model is dynamic and provides results during short-term transients (few seconds to few days) as well as at the end of long irradiations (few years). This one-dimensional code was developed for accident conditions that lead to high fuel temperature, but it is also applicable to normal operating conditions. The activity calculations account for contributions from both volatile and nonvolatile fission products. They also account for radioactive decay during all the above processes and for the effect of precursors. The predictions of GASOUT were found to be in reasonable agreement with the steady-state predictions (for stable gas) of the NOTPAT code on which it is based. Furthermore, agreement was also reasonable to exact solutions from the Booth diffusion model, to data from the CONTACT-1 series of experiments and from the direct electric heating experiments, and to American Nuclear Society Standard 5.4.