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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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Fusion Science and Technology
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.”
Ryan G. McClarren, Daniel Holladay
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 600-604
IFE Design & Technology | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12449
Articles are hosted by Taylor and Francis Online.
We present the first semi-analytic radiation transport solutions for the three-temperature (3-T) model: the equations that couple radiation, electron, and ion energy density in a dense plasma. The problem we solve is the 3-T version of the Su-Olson problem considered in a recent radiation diffusion study for verification of a production HEDP code. After linearizing the equations, integral transforms are used to solve the equation, and the inverse transforms are computed numerically after considerable simplication. The results are compared to 2-T transport and 3-T diffusion solutions.