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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.”
O. Graf, A. Bayer
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 50-71
Technical Paper | Nuclear Safety | doi.org/10.13182/NT91-A35533
Articles are hosted by Taylor and Francis Online.
Realistic probabilistic safety assessment and risk studies for nuclear power facilities and for emergency planning call for detailed knowledge of the shielding properties of buildings. The investigations described here focus on the building types encountered in central Europe, with its high population density. The necessary dose rate calculations are performed with a new combination of the point kernel integration technique (the QAD-CG-E code) and the Sn transport method (the DOT 4.2 code). This procedure seems to be optimal for irregular three-dimensional shielding structures, providing good accuracy and performing a great number of individual calculations. The validity and accuracy of the procedure are checked by Monte Carlo calculations (the SAM-CE code) and by recalculating a U.S. shielding experiment. The evaluation of literature and the examination of data led to a list of 12 building types representative of those in central Europe. The geometries of the buildings are composed of ∼150 to 300 basic geometrical bodies. This is the input for the QAD-CG-E computer code (i.e., combinatorial geometry). Shielding calculations are performed for these 12 building types assuming contamination by 137Cs. The high-rise apartment and row house building types show a good shielding efficiency (a shielding factor <0.1), while the bungalow and prefabricated house offer the lowest shielding value (a shielding factor of 0.3). The other building types have a mean shielding factor value of 0.1. Additional calculations with 131I and 140La show the influence of the gamma energy on the shielding factor. Moreover, gamma fields or spatial dose rate distributions are calculated for a semidetached house, a prefabricated house, and a high rise. The results are presented by isodose lines drawn through vertical and horizontal cross sections of the buildings.
