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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
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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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.”
Zhenyu Yao, Akihiro Suzuki, Denis Levchuk, Takayuki Terai
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 865-869
Technical Paper | First Wall, Blanket, and Shield | doi.org/10.13182/FST07-A1601
Articles are hosted by Taylor and Francis Online.
SiC coating is formed on the reduced activation martensitic steel JLF-1 by radio frequency sputtering. The coating thickness decreases with increased deposition temperature and increases with increased deposition time. The atomic ratio of Si and C nears 1:1 in coating, while oxygen fraction exists. The coating shows a trend that the crystallization starts from deposition temperature of 723 K, though the coating is amorphous. In this study, the deuterium permeation flux of bare JLF-1 is lower about two orders of magnitude than that of Eurofer97, which is thought as a reason of oxidation of bare JLF-1 during test. The deuterium permeation flux of coated JLF-1 is about one to two orders of magnitude lower than that of bare JLF-1.
