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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.”
P. Y. Li, C. J. Pan, B. L. Hou, S. L. Han, Z. C. Sun, F. Savary, Y. K. Fu, R. Gallix, N. Mitchell
Fusion Science and Technology | Volume 61 | Number 2 | February 2012 | Pages 141-146
Technical Paper | First Joint ITER-IAEA Technical Meeting on Analysis of ITER Materials and Technologies | doi.org/10.13182/FST12-A13380
Articles are hosted by Taylor and Francis Online.
The research and development of manufacture-related technology for ITER magnet supports is one of the tasks for construction. AISI 316LN austenitic stainless steel has been developed and tested as the main raw material. The material shows excellent mechanical properties at room temperature, 77 K, and 4.2 K. An alternative design for the toroidal field support manufacture without welding was carried out. The structural analysis shows no stress concentration and buckling in the present design during ITER operation. However, further engineering tests of the structural stability under various load combinations are also scheduled. A brazed connection to attach the cooling pipes to the support plates is suggested. Several kinds of candidate brazing fillers, such as Sn-Pb-, Ag-, and Cu-based alloys have been developed. The tensile strength of the brazed solders is up to 400 MPa at 77 K for the Ag-based and Cu-based fillers. For correction coil support, the plasma spray insulation coating was developed and introduced.