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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.”
Samet Y. Kadioglu, Dana A. Knoll, Cassiano de Oliveira
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 132-143
Technical Paper | doi.org/10.13182/NSE09-07
Articles are hosted by Taylor and Francis Online.
Coupling neutronics to thermomechanics is important for the analysis of fast burst reactors because the criticality and safety study of fast burst reactors depends on the thermomechanical behavior of fuel materials. For instance, the shutdown mechanism or the transition between supercritical and subcritical states is driven by the fuel material expansion or contraction. The material expansion is due to the temperature gradient that results from fission power. In this paper, we introduce a numerical model for coupling of neutron diffusion and thermomechanics in fast burst reactors. The goal is to have a better understanding of the relation between the reactivity insertion and the thermomechanical response of fuel materials. We perform a nondimensional analysis of the coupled system that provides insight into the behavior of the transient. We also provide a semianalytical solution model to the coupled system for partial verification of our numerical solutions. We studied material behavior corresponding to different levels of reactivity insertion.