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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.”
Satoshi Sato, Hideyuki Takatsu, Yasushi Seki, Toshihisa Utsumi
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1129-1133
Neutronics Experiments and Analyses | doi.org/10.13182/FST96-A11963100
Articles are hosted by Taylor and Francis Online.
Shielding analyses of the inboard blanket, the vacuum vessel and the Toroidal Field Coil (TFC) in International Thermonuclear Experimental Reactor OTTER) were performed by Monte Carlo and 2-dimensional discrete ordinate methods taking the radiation streaming through the 20 mm wide gap between the adjacent blanket modules into account, and their peak nuclear responses were evaluated The nuclear responses of the TFC could fully satisfy the radiation limits. On the other hand, the helium production rates of the branch pipe, the leg and the front surface of the vacuum vessel behind the gap were about 2-3 times higher than the radiation limit at the end of the operation, i.e. the neutron fluence of 3 MWa/m2. So the shielding module is required to be increased by 80 mm to satisfy the radiation limit. Also, shielding analyses for 20 - 100 mm wide gaps were performed, and it was found that the gap width could be increased by up to 50 mm from the TFCs protection for their peak nuclear responses point of view.