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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.”
R. T. McGrath, A. J. Russo, R. B. Campbell, R. D. Watson
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1805-1816
Plasma-Facing Component | doi.org/10.13182/FST92-A29981
Articles are hosted by Taylor and Francis Online.
Tokamaks currently in operation deposit on the order of 1–30 MW/m2 onto plasma facing surfaces during normal operation and hundreds of MW/m2 for shorter periods of time (0.1–3 ms) during disruptions. Disruption deposited energies on future high-power tokamaks may be well in excess of 20 MJ/m2 Design of plasma facing components (PFCs) for such severe environments requires considerable advancements in materials development, armor tile bonding to actively cooled substrates, heat transfer, and many other areas of engineering concern. Considerable improvements in PFC performance, reliability and lifetime can also be accomplished through improved understanding and control of the edge plasma boundary layer. This paper covers both engineering and edge plasma physics issues that must be addressed in the development of reliable PFCs for ITER. Several specific examples are addressed since a complete treatment of all critical development issues would be lengthy. Topics covered include impurity generation and transport in the boundary layer plasma, materials response to intense pulsed disruption heat loads, runaway electron generation during disruptions, high heat flux performance and PFC fabrication issues. These topics are illustrative examples of the variety of complex issues that must be addressed in the development and design of PFCs.