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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.”
R. N. Nair, Y. S. Mayya, V. D. Puranik
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 53-69
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3689
Articles are hosted by Taylor and Francis Online.
A generic method has been developed to evaluate the reasonable upper-bound (RUB) dose from near-surface radioactive waste disposal facilities through a drinking water pathway. This generic method has been developed by applying a safety assessment model to seven near-surface radioactive waste disposal sites in India. The concentrations and effective radiation dose rates due to different radionuclides are evaluated at different distances from the disposal facilities. The peak dose rates received by members of the public at these distances are given per unit nuclear power capacity at the site [mSv/yr per GW(electric)yr]. The product of these normalized peak dose rates and the total existing or projected nuclear power capacity at a site [GW(electric)yr] will indicate the RUB dose rates from the near-surface disposal facility through a drinking water pathway at different distances. Results indicate that the sites can be grouped into two categories: (a) sites having groundwater velocity >10 cm/day (category 1) and (b) sites having groundwater velocity <10 cm/day (category 2). The variation in the dose rates between each category of sites is found to be small. Based on this finding, a generic method has been developed to evaluate the RUB dose rates to members of the public from the near-surface radioactive waste disposal facilities as a function of distances and nuclear power capacity. It is observed that the RUB dose rates at 1, 2, and 3 km are ~0.03, 0.02, and 0.01 mSv/yr, respectively, for category 1 sites for a nuclear power capacity of 1 GW(electric). These dose rates are reduced by a factor of 2 for category 2 sites. This generic method is found useful for the screening analysis of proposed low-level radioactive waste disposal sites as it estimates the RUB effective dose rates as a function of distance and nuclear power capacity for different categories of sites.