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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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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.”
J. T. Ream, R. P. Varnes
Nuclear Science and Engineering | Volume 13 | Number 4 | August 1962 | Pages 325-337
Technical Paper | doi.org/10.13182/NSE62-A26174
Articles are hosted by Taylor and Francis Online.
It was planned to test full scale U02 test elements in the SRE core. Before doing this, an analysis of the transient behavior of the system in part and the whole was carried out. This analysis concerns the problem of determining transient thermal gradients in the Sodium Reactor Experiment core due to the inability of the after-scram braked flow of the sodium to properly cool the U02 fuel test elements. The analysis showed that the UO2 fuel elements could not be irradiated at the desired core position for maximum power density without exceeding the allowable transient thermal gradient limit. It was necessary to shift them to a position of 25% lower power. An experimental scram of the SRE verified these results for the 19-rod cluster type element. It was possible to concentrate the investigation on the region of the core containing the U02 test elements using the assumption that the steady-state relationship between core pressure drop and reactor flow was valid during flow coastdown. Distributed spatial parameter effects were approximated by a “lumped”-parameter model and were incorporated in sets of coupled finite difference equations which were then solved by use of a general purpose dc analogue computer. The transient flow in the test elements were computed from the SRE quasi-steady-state pressure drop as a function of time. The higher sodium outlet temperature in the U02 test element channels results in an elevation head greater than the elevation head in an SRE channel. This nonlinear buoyant force could not be neglected because it significantly increases the transient flow in the U02 fuel element and stabilizes the channel outlet temperature.
