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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.”
Chien C. Lin, J. H. Chao
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 244-250
Technical Paper | Radioisotopes | doi.org/10.13182/NT07-A3896
Articles are hosted by Taylor and Francis Online.
The main function of radiochemical surveillance in a nuclear power plant is to monitor the transport of radioactive materials in and out of various systems, including the fuel integrity evaluation and the control of radioactive material release to the environment. Radiochemical analyses of iodine activities in the reactor coolant to assess fuel integrity during normal operation and to characterize the nature of fuel failure are demonstrated. Assessment of fission products released by the so-called recoil process is emphasized in the study. Measurements of 91Sr and 92Sr in reactor water are recommended as the recoil indicators and to determine the fuel particle contamination on fuel surfaces. In an operating BWR/6 with a recoil level at ~1.2 × 1013 fission/s operated at ~2980 MW(thermal), ~30 g of fuel particle contamination was estimated.