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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.”
Yu-Hung Shih, Mei-Ya Wang, Tsuey-Lin Tsai, Tsung-Kuang Yeh
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 92-103
Technical Paper | doi.org/10.1080/00295639.2022.2102392
Articles are hosted by Taylor and Francis Online.
Activated corrosion products deposited on the surfaces of fuel rods and pipelines contribute the majority of the radiation level in the primary system piping of a light water reactor and would have a significant impact on the safety of maintenance personnel or those involved in future decommissioning work. A computer model for site-specific applications, by the name of ACP_BWR, was developed to predict the distribution of activated corrosion products in the primary coolant circuit of a boiling water reactor (BWR). The prediction results were in reasonably good agreement with the data taken by periodic and in situ measurements at three locations after permanent shutdown of the BWR. Our analyses indicated that the 60Co, 54Mn, 58Co, and 59Fe activities in the core bypass, upper plenum, and lower downcomer regions were higher than those at other regions of the Chinshan Unit 1 reactor. Accordingly, the dose rates resulting from the activated corrosion products deposited at regions close to either side of the core shroud were comparatively high, surpassing those induced by neutron activation at these regions.