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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.”
Thomas B. Rezentes, Mark A. Prelas, Eric Lukosi, Matthew L. Watermann, Jack Crawford, and Richard H. Olsher
Nuclear Technology | Volume 187 | Number 1 | July 2014 | Pages 96-102
Technical Note | Radiation Transport and Protection | doi.org/10.13182/NT11-105
Articles are hosted by Taylor and Francis Online.
A computer-based investigative technique, using the Los Alamos Monte Carlo code MCNP5 version 1.51 (Radiation Safety Information Computational Center), was completed to assess the shallow dose equivalent (SDE) reported on the Landauer, Inc.,TM Luxel+ optically stimulated light (OSL) dosimeter. Experimental test irradiations were conducted on 18 OSL dosimeters through various controlled exposures to the source (10 mCi 90Sr). The reported SDE for each test irradiation was compared to the results for SDE calculated using MCNP5. All test irradiation experiments were conducted with the 90Sr source placed in direct contact with the dosimeter with slight placement changes across the dosimeter face. It was found that these slight adjustments caused vast differences in reported doses by Landauer. The SDE determined in a tissue matrix using MCNP5 was studied for two of the dosimeter badge geometries, and it was found that some qualitative agreement exists between the reported and simulated doses in contradiction with the experimental results. Further simulated analysis was not conducted because precise source-dosimeter geometries and the algorithm used by Landauer to analyze its Luxel+ OSL dosimeters were not known. These results indicate that a future study should be conducted with more rigorous simulated benchmarking to verify these results.
