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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
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.