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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.”
Nicholas Chornoboy, Alexandra Levinsky, Charles Kitson, Blair P. Bromley
Nuclear Technology | Volume 204 | Number 1 | October 2018 | Pages 110-118
Technical Note | doi.org/10.1080/00295450.2018.1454229
Articles are hosted by Taylor and Francis Online.
Lattice physics depletion calculations were performed to obtain postburnup fuel compositions for several candidate advanced heavy water reactor fuels. These fuel compositions were used as input for a deep geological repository (DGR) modeling tool for hydrogeology simulations to simulate the transport of radionuclides to the surface, to find the radionuclides that reach the surface path through the biosphere, and to estimate the hypothetical dose rate to humans located above the DGR.
Three primary factors were found to contribute to surface dose rate: burnup, composition of the primary waste matrix, and percentage of thorium in the fuel. Higher burnup and thorium percentage contribute to increased surface dose rates through increased 129I production, while a primarily uranium waste matrix increases surface dose rate through faster dissolution leading to increased radionuclide release rate from the fuel. For all the hypothetical fuels investigated, the estimated dose rates are well within the Nuclear Waste Management Organization’s hypothetical DGR’s acceptance criterion of 0.3 mSv/year.
