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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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.”
B. A. Kalin, A. N. Suchkov, V. T. Fedotov, O. N. Sevryukov, A. A. Ivannikov, A. A. Polyansky, I. V. Mazul, A. N. Makhankov, A. A. Gervash, P. S. Dzhumaev, V. L. Yakushin, V. I. Polsky
Fusion Science and Technology | Volume 61 | Number 2 | February 2012 | Pages 147-153
Technical Paper | First Joint ITER-IAEA Technical Meeting on Analysis of ITER Materials and Technologies | doi.org/10.13182/FST12-A13381
Articles are hosted by Taylor and Francis Online.
Rapidly quenched ribbon-type filler metals of the systems of Cu-Sn-In-Ni-Mn-P (STEMET® 1108) and Cu-Ti-Be (STEMET 1204M) for brazing of high-heat-flux elements of ITER were developed at National Research Nuclear University (NRNU) Moscow Engineering Physics Institute (MEPhI) together with D.V. Efremov Scientific Research Institute of Electrophysical Apparatus (SRIEA).The technological brazing parameters of the joints of beryllium with bronze (CuCrZr)-Be-CuCrZr ("rapid brazing" by an electron beam) and tungsten with bronze (CuCrZr)-W-CuCrZr (vacuum brazing in a furnace) were improved by the filler metals obtained. It is shown that under rapid brazing it is possible to minimize the Be2Cu intermetallic layer thickness between the filler metal and beryllium up to 1 to 1.5 m in comparison with that of 8 to 10 m obtained in brazing in a furnace with resistive heating and to avoid weakening of bronze (CuCrZr). Brazing of W-CuCrZr was successful in completely dissolving the alloying components of the filler metal in the bronze base and obtaining a joint without a transition layer.A complex of metallographic, mechanical, and thermocycling tests of the brazed joints obtained was carried out. It is shown that the brazed seam width (for rapid brazing of Be-CuCrZr) and the brazing zone morphology do not change during the annealing (at 300°C for 100 h) and thermocycling tests (1000 cycles at 5 and 8 MW/m2). The brazed joints of Be-CuCrZr obtained by rapid brazing withstood 4500 cycles at the thermal load of 12 MW/m2 and 1000 cycles at 13.5 MW/m2. The maximum thermal load achieved at screening was 16 MW/m2. It is established that under irradiation by pulsed deuterium plasma flows from the end surface of brazed joints of tungsten with copper-base heat-removing alloys using a hard irradiation parameter (W = 5 MW/cm2), the joint of monocrystal tungsten with bronze CuCrZr brazed by the STEMET 1204M filler metal has the highest thermal stability.It is shown that neutron irradiation (at a fluence of 1.8 × 1020 n/cm2 with a neutron energy >0.1 MeV, at 200°C) does not result in weakening of the W-CuCrZr brazed joint.
