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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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ANS standard updated for determining meteorological information at nuclear facilities
Following approval in October from the American National Standards Institute, ANSI/ANS-3.11-2024, Determining Meteorological Information at Nuclear Facilities, was published in late November. This standard provides criteria for gathering, assembling, processing, storing, and disseminating meteorological information at commercial nuclear power plants, U.S. Department of Energy/National Nuclear Security Administration nuclear facilities, and other national or international nuclear facilities.
Jeremy A. Roberts, Bradley T. Rearden, Paul P. H. Wilson
Nuclear Science and Engineering | Volume 173 | Number 1 | January 2013 | Pages 43-57
Technical Paper | doi.org/10.13182/NSE10-109
Articles are hosted by Taylor and Francis Online.
This paper presents a method for determining partial biases and bias uncertainties for application in fission product burnup credit criticality safety analysis. The contribution of each nuclide to the overall system keff bias and the bias uncertainty are determined via the generalized linear least squares method. Where experimental benchmarks are available to validate specific nuclides, sensitivity and uncertainty analysis is used to project biases observed in the benchmarks to biases appropriate for the safety system. Two weighting schemes are proposed to produce an overall bias in the safety system from several single partial biases. Finally, these methods are used to determine partial biases for 149Sm and 103Rh from two experiment series and to apply these biases to a representative used fuel safety system. The biases obtained are compared to bounding estimates, and the sensitivity of the results to relevant assumptions is addressed.