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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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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.”
Shih-Jen Wang, Ming-Song Lin
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 156-161
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34553
Articles are hosted by Taylor and Francis Online.
The characteristics of xenon dynamics are simulated, and related parameters are identified in the Taiwan Research Reactor. A xenon transient for a 20% stepwise decrease from 85.6% rated power is performed and simulated with design data. The trends in the moderator levels are similar in the test and in the simulation. However, there are discrepancies in the magnitude and shape. Because no reactivity feedback occurs for 2 h after the power change, except for xenon poisoning, a parameter optimization method is applied to identify the migration area and the initial neutron flux by minimizing the integrated square error of the moderator level from 2 to 20 h after the power change. The optimized moderator level fit the test result very well, and the identified parameters are reasonably close to the experimental data.
