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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.
E. Wakai, T. Kikuchi, T. Yokomine, M. Yamamoto, M. Soldaini, A. Polato
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 246-251
IFMIF | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14142
Articles are hosted by Taylor and Francis Online.
International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activity (IFMIF/EVEDA) was started in 2007 in the joint program between Japan (JA) and the European Union (EU). IFMIF has mainly three facilities, i.e., test facility, lithium target facility, and accelerator facility. In this program, there are three subjects of the JA team in the test facility such as the design of the post irradiation examination (PIE) facility, the design and validation of the high flux test module, and the evaluation of the small size specimen technique. In this paper, the test matrix of the IFMIF was evaluated. All test matrixes depend on the requirement of a database preparation schedule and the irradiation volume of irradiation modules such as high flux test module (HFTM), medium flux test module (MFTM) and low flux test module (LFTM), but the engineering design of HFTM is mainly proceeding. Accordingly, the lists of the experiments of small size specimens set in the HFTM to be performed in the PIE laboratories have been carefully analyzed. In the design of HFTM, two types of HFTM are proposed for RAFM steel irradiation by the EU KIT team and for the advanced materials by the JA team, and the difference was summarized.