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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.
Keith Searson, Fabrice Fleurot, Andrew Cooper, Pat Cowan
Nuclear Technology | Volume 175 | Number 1 | July 2011 | Pages 259-263
Technical Paper | Special Issue on the 16th Biennial Topical Meeting of the Radiation Protection and Shielding Division / Radiation Transport and Protection | doi.org/10.13182/NT11-A12297
Articles are hosted by Taylor and Francis Online.
A computer-aided design (CAD) import and tracking system, OiNC, has been developed that is currently being incorporated into the MONK and MCBEND criticality and shielding codes. The system enables analysts to take advantage of the advanced geometry modeling capabilities provided by the solid CAD modelers Autodesk Inventor and Solidworks. Various tracking acceleration techniques are implemented in order to reduce calculation time, including the full or partial automatic conversion of the CAD model to constructive solid geometry (CSG) form. For the criticality benchmark model detailed here, the overall calculation run time for a CAD-based geometry was found to be just 14% longer than an equivalent text-based CSG model. OiNC uses analytical surface descriptions, with full NURBS support, avoiding the approximations and problems associated with meshing. However, meshed models can still be imported and tracked, enabling shielding and criticality calculations to be performed, for example, on impact simulated finite element models.