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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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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.”
A. Stäbler, J. Sielanko, S. Götz, E. Speth
Fusion Science and Technology | Volume 26 | Number 2 | September 1994 | Pages 145-152
Technical Paper | Plasma Heating System | doi.org/10.13182/FST94-A30338
Articles are hosted by Taylor and Francis Online.
Powerful neutral beams used in many present-day magnetic fusion devices to heat the plasma to high temperatures must pass a region of finite background pressure where the magnetic stray field is rather high. Reionization of neutral beam particles and their subsequent deflection onto walls may lead to serious power loadings if no proper protection is provided. The simulation of this problem for the neutral beam injection system of the ASDEX-Upgrade tokamak is examined. The magnetic field distribution and the particle trajectories are calculated in full three-dimensional geometry. The statistical methods applied to simulate the ∼106 beam particles necessary to obtain a reliable power density distribution on the various surfaces of the duct region are described in some detail. Results are given for different magnetic field configurations of the tokamak. Because of the focusing effect of the strongly varying magnetic field, power densities in excess of 2 MW/m2 are found in extreme cases. Additional large area shieldings are installed to protect the most exposed regions of the entrance port of the vessel.