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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Strontium: Supply-and-demand success for the DOE’s Isotope Program
The Department of Energy’s Isotope Program (DOE IP) announced last week that it would end its “active standby” capability for strontium-82 production about two decades after beginning production of the isotope for cardiac diagnostic imaging. The DOE IP is celebrating commercialization of the Sr-82 supply chain as “a success story for both industry and the DOE IP.” Now that the Sr-82 market is commercially viable, the DOE IP and its National Isotope Development Center can “reassign those dedicated radioisotope production capacities to other mission needs”—including Sr-89.
Jeffrey Doody, Robert Granetz, Damao Yao, William Beck, Lihua Zhou, Zibo Zhou, Lei Cao, Xuan Xia, Rui Vieira, Stephen Wukitch, James Irby
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 582-586
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-928
Articles are hosted by Taylor and Francis Online.
Chinese Academy of Sciences Institute of Plasma Physics (ASIPP) Experimental Advanced Superconducting Tokamak (EAST) has designed and built a new outer divertor with an ITER-like cooling system. As part of a joint collaboration, the Plasma Science and Fusion Center at MIT performed analyses on the EAST design to determine loading, stresses and deflections due to the eddy currents and halo currents occurring during a disruption. The analysis was done using the finite element program COMSOL using techniques developed at MIT to recreate actual tokamak discharges from measured data. This technique has been used successfully to recreate discharges from Alcator C-Mod, a high field tokamak with TZM tiles at the Plasma Science Fusion Center at MIT, and allows us to recreate the fields for any disruption from the EAST data base. For the new divertor, an upward moving disruption was chosen as the design scenario.
The plasma filament model predicts fields, eddy currents and loads due to a disruption, but the divertor will also be exposed to halo currents. The new EAST divertor borrows its cooling system design from ITER where the plasma facing tungsten tiles are water cooled by a CuCrZr manifold and pipes attached to the tiles. Halo currents traveling down these tubes and crossing the toroidal field will result in large loads in these components, and COMSOL is used to predict the stresses and deflections. The model predicts that the EAST divertor will survive the combined loading due to the eddy and halo currents.