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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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.”
Milan Vujović, Miloš Vujisić
Nuclear Technology | Volume 208 | Number 11 | November 2022 | Pages 1649-1665
Technical Paper | doi.org/10.1080/00295450.2022.2070354
Articles are hosted by Taylor and Francis Online.
Several select geopolymer, polymer, and composite materials are considered as potential candidates for the inner shielding in containers used for storage and disposal of low- and intermediate-level radioactive waste, from the perspective of radiation effects. The suitability of the probed materials is examined through Monte Carlo simulations, which yield absorbed dose values in container inner shieldings of various compositions and dimensions. The radioactive waste considered in the simulation models contains 60Co or 137Cs and is placed inside standard 216.5-L (55-gal) drums, in either compacted or solidified form. The influence of container stacking, in either a storage or a disposal environment, on the dose in the shielding is also taken into account. The simulation results are used for calculating the dose-dependent overpressure within the container caused by the gas generated in the inner shielding through radiolysis. Two types of waste activity limits are determined for each of the researched shielding materials: one below which the overpressure decreases after the initial heat-induced jump and another that results in an overpressure that stays just below the maximum tolerable value. Dose-dependent changes of the polymer and composite shielding materials’ molecular weights are also calculated. The obtained results show that with regard to the radiation effects caused by the investigated sources, the examined materials are compatible with the proposed use as inner shielding in radioactive waste containers.