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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.
M. Glugla, R. Kraemer, R.-D. Penzhorn, T.L. Le, K.H. Simon, K. Günther, U. Besserer, P. Schäfer, W. Hellriegel, H. Geißer
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 625-629
Tritium Processing | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30473
Articles are hosted by Taylor and Francis Online.
A fuel clean-up process for all plasma exhaust gases from DT fusion machines, based on catalytic conversion reactions combined with permeation of hydrogen isotopes through palladium/silver, has been developed. The complete process has already been proven with relevant concentrations of tritium at laboratory scale. On the basis of the results obtained the technical facility ‘CAPRICE’ was designed, and is now under tritium operation at the Tritium Laboratory Karlsruhe (TLK). The facility is being used to demonstrate the process on a target throughput of 10 mol/h DT and 1 mol/h tritiated and non-tritiated impurities. Full scale experiments with hydrogen and deuterium have been completed to verify the design parameters of the facility and to gain detailed knowledge on the performance of the different subsystems under a variety of experimental conditions. Decontamination factors were obtained from these experiments as well as from first tritium runs employing about 350 Ci (0.5 %) tritium in deuterium.