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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
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.”
Insoo Jim, Mohamed Abdou
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2159-2168
Blanket Shield and Neutronic | doi.org/10.13182/FST92-A30040
Articles are hosted by Taylor and Francis Online.
Activation analysis for the cavity of the PROMETHEUS ICF design, which uses a wetted first wall protection scheme, has been performed. It has been found that the PROMETHEUS cavity produces about 0.9 Ci/W of thermal power at shutdown after the full 30 years operation, which is about the same amount of radioactivity of other ICF and MCF fusion designs with low activation materials. It was possible, however, to reduce the radioactivity inventory level in the shield by one to three orders of magnitude by introducing a new shield design that uses B4C, Pb, SiC and water instead of using the conventional concrete shield. Furthermore, the effect of using the spherical and cylindrical modeling on the prediction of radioactivity in the first wall has been studied. It has been found that the cylindrical model with a point neutron source at the center of the cylinder reduces the radioactivity of the short half-life products to about 80% of the values that would be obtained by using purely spherical modeling. Finally, the 210Po problem associated with the use of lead has been analyzed. It is shown that 210Po produced from neutron interactions with lead is more important than that produced from the bismuth impurity (40ppm) existing in lead if the machine is operated over ∼1 year.