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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
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Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
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.