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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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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.”
Bahram Nassersharif, James S. Peery, Evelyn M. Mullen, Stephen R. Behling
Nuclear Technology | Volume 94 | Number 1 | April 1991 | Pages 28-43
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A16219
Articles are hosted by Taylor and Francis Online.
This study evaluates two significantly different models of a Westinghouse 414 reactor system using the TRAC-PF1/MOD1 computer code for a small-break loss-of-coolant accident (SBLOCA). A coarse threedimensional model of the reactor vessel is developed. In the coarse model, three of the four reactor coolant loops are combined into one loop. A detailed three-dimensional model of the reactor vessel is also developed. In the detailed model, each of the four coolant loops is modeled separately. Both models are run to steady-state convergence until the calculated system parameters are in good agreement. In addition, the steady-state results of both models closely match operational parameters given in the final safety analysis report. From the self-consistent steady-state conditions, a 60-s transient calculation is performed with each model. The transient simulates a 4-in. SBLOCA. The overall results of code predictions for the two models closely agree, and the vessel global parameters for the two models are also in good agreement. However, the computer times for the two calculations are significantly different. The detailed model provides additional information that is unavailable with the less detailed model, such as temperature and void fraction distributions throughout different regions of the vessel. During the 60-s transient, the upper head in the detailed model shows extensive voiding. The upper head in the coarse model also shows voiding; however, the extent and exact location of the voiding are not available in the coarse model. During this transient, the core region does not show extensive voiding; however, the detailed model shows some localized boiling. The results indicate that the coarse model is sufficient for 4-in. SBLOCA studies. The computer time associated with TRAC-PF1/MOD1 calculation of the extremely detailed model is ∼100 times longer than the coarse model.