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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.
Benjamin R. Hanna, Daniel F. Gill, David P. Griesheimer
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 367-378
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19425
Articles are hosted by Taylor and Francis Online.
An integrated thermal-hydraulic feedback module has previously been developed for the Monte Carlo transport solver MC21. The module incorporates a flexible input format that allows the user to describe heat transfer and coolant flow paths within the geometric model at any level of spatial detail desired. The effect that the varying levels of spatial homogenization of thermal regions has on the accuracy of the Monte Carlo simulations is examined in this study. Six thermal feedback mappings are constructed from the same geometric model of the Calvert Cliffs core. The spatial homogenization of the thermal regions is varied, giving each scheme a different level of detail, and the adequacy of the spatial homogenization is determined based on the eigenvalue produced by each Monte Carlo calculation. The purpose of these numerical experiments is to determine the level of detail necessary to accurately capture the thermal feedback effect on reactivity. Several different core models are considered: axial flow only, axial and lateral flow, asymmetry due to control rod insertion, and fuel heating (temperature-dependent cross sections). The thermal results generated by the MC21 thermal feedback module are consistent with expectations. Based on the numerical experiments conducted, it is concluded that the amount of spatial detail necessary to accurately capture the feedback effect on reactivity is relatively small. Homogenization at the assembly level for the Calvert Cliffs pressurized water reactor model results in a power defect similar to that calculated with individual pin cells modeled as explicit thermal regions.