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Division Spotlight
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
Standards Program
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.”
Bernard André, Gérard Ducros, Jean Pierre Lévêque, Morris F. Osborne, Richard A. Lorenz, Denis Maro
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 23-50
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35221
Articles are hosted by Taylor and Francis Online.
During the 1970s, reactor safety authorities developed increasing interest in methods for accurately predicting the extent of hazards associated with severe accidents in light water reactors (LWRs). In response to these concerns, out-of-pile experimental projects were initiated by the U.S. Nuclear Regulatory Commission and the French Nuclear Protection and Safety Institute, at Oak Ridge National Laboratory (ORNL) and the Commissariat à l’Energie Atomique (CEA), respectively. Both experimental efforts were designed for source term characterization of the fission products (FPs) released from LWR fuel samples under test conditions representative of severe accidents, i.e., in oxidizing or reducing atmospheres at temperatures up to 2700 K (at ORNL) and 2570 K (at CEA). The experimental devices, procedures, and parameters are described. The combined database of available results is summarized and related to experimental conditions. Using Booth diffusion theory, diffusion coefficients of the FPs were calculated, and their evolution with temperatures in the 1070 to 2700 K range were plotted. The results show the good agreement between the independently determined ORNL and CEA FP diffusion coefficient values. By plotting the data in Arrhenius fashion, it has been possible to do the following: