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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.”
Muhammad Altahhan, Sandesh Bhaskar, Paolo Balestra, Jason Hou, Maria Avramova (NCSU), Nicholas Smith (Southern Co.)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 1248-1256
In this study, a hybrid two-dimensional (2D) / three-dimensional (3D) Liquid Fuel Molten Salt Reactor (LFMSR) core is modelled using the Multi-physics C++ code GeN-Foam (General Nuclear Foam). GeNFoam has three main sub-solvers - for neutron kinetics, thermal hydraulics, and thermal mechanics. A steady state analysis of a simplified 2D LFMSR model has been performed assuming rotational symmetry to cross validate the code with the commercial ANSYS Computational Fluid Dynamics (CFD) code Fluent. The calculations showed a very good agreement between the two codes allowing moving onto a 3D model simulation. A coupled 3D neutron kinetic and CFD steady state analysis of the 3D LFMSR core has been performed modeling one quarter of the core using the core symmetry to reduce the computational time. The GeN-Foam neutron kinetics sub-solver has been designed to consider also the drifting of the delayed neutrons precursors in LFMSR, a capability not yet implemented in the most of current neutron kinetics codes. The mixed Uranium and Plutonium chloride fuel has been selected in this preliminary study. The calculation results meet the expectations showing that GeN-Foam has all the features necessary for LFMSR design modeling and simulation. The delayed neutrons precursors behavior is as expected - the longer-lived isotopes accumulate near the outlet while the short-lived ones lay at the generation location. The calculated maximum temperature is close to the expected one and the velocity profile is consistent with a low viscosity, high density fluid velocity profile.