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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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.”
Oleg G. Povetko
Nuclear Technology | Volume 163 | Number 1 | July 2008 | Pages 31-37
Technical Paper | High-Level Radioactive Waste Management | doi.org/10.13182/NT08-A3967
Articles are hosted by Taylor and Francis Online.
Radioactive waste-handling operations at a potential high-level radioactive waste (HLW) geologic repository at Yucca Mountain, Nevada, would involve receiving, processing, aging, and emplacing HLW equivalent to 70 000 t of heavy metal. This paper presents results of an independent analysis of the external radiation dose fields for various designs at a potential repository underground facility, performed at the Center for Nuclear Waste Regulatory Analyses. In order to analyze dose fields, radiation source terms have been developed for commercial spent nuclear fuel (SNF) assemblies. Full-scale three-dimensional models of waste packages and underground repository drifts were used in the Monte Carlo radiation transport simulations. Radiation dose rates along the drifts have been evaluated for multiple waste packages for SNF-emitted photons, neutrons, and 60Co photons. Analysis shows that SNF photons contribute >68%, 60Co photons contribute <30%, and neutrons contribute <2% to the total dose rates. The contribution of photons scattered off the drift walls is <10% of the total dose rates. The drift elbow significantly blocks direct radiation shine and reduces scattered dose rates at the junction of turnout and main access drifts where workers could be present.
