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Remembering Joseph M. Hendrie
Joseph M. Hendrie
To those of us who knew Joe, even prior to his appointment as chair of the Nuclear Regulatory Commission, it is an understatement to say that he was a larger-than-life member of the nuclear science and technology enterprise. He was best known to the broader community for two major accomplishments: the design and construction of the High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory and the creation of the standard review plan (SRP) for the U.S. Atomic Energy Commission.
In addition to the products of these endeavors becoming major fundaments to their respective communities, they were uniquely Joe. The safety analysis report for the HFBR was written essentially single-handedly by him. This was true of the SRP as well, which became the key safety review document for the NRC as it performed safety reviews for the growing number of power reactor applications in the United States. His deep technical knowledge of nuclear engineering and his extraordinary management skills made this possible.
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.