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Remembering Charles E. Till
Charles E. Till
Charles E. Till, an ANS member since 1963 and Fellow since 1987, passed away on March 22 at the age of 89. He earned bachelor’s and master’s degrees from the University of Saskatchewan and a Ph.D. in nuclear engineering from Imperial College, University of London. Till initially worked for the Civilian Atomic Power Department of the Canadian General Electric Company, where he was the physicist in charge of the startup of the first prototype CANDU reactor in Canada.
Till joined Argonne National Laboratory in 1963 in the Applied Physics Division, where he worked as an experimentalist in the Fast Critical Experiments program. He then moved to additional positions of increasing responsibility, becoming division director in 1973. Under his leadership, the Applied Physics Division established itself as one of the elite reactor physics organizations in the world. Both the experimental (critical experiments and nuclear data measurements) and nuclear analysis methods work were internationally recognized. Till led Argonne’s participation in the International Nuclear Fuel Cycle Evaluation (INFCE), and he was the lead U.S. delegate to INFCE Working Group 5, Fast Breeders.
Teruya Tanaka, Hiroaki Muta, Yoshimitsu Hishinuma, Hitoshi Tamura, Takeo Muroga, Akio Sagara
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 705-710
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST15-110
Articles are hosted by Taylor and Francis Online.
Performance and applicability of hydride shielding materials are investigated in the helical reactor FFHR-d1 design. Performance of ZrH2 and TiH2 in fast neutron shielding are close to that of WC, which is most effective among candidate materials, for both in-vessel and out-vessel use. The investigation confirms that neutron shielding performance of a two-layered ferritic steel (FS)/ZrH2 or TiH2 shield is similar to that of a one-layered ZrH2 or TiH2 shield with the same total thickness. This shielding property is an important feature to maintain consistency with the structure design of FFHR-d1. In attenuation of direct neutrons from the core plasma in a bending duct, the hydride duct walls show superior performance compared with FS + B4C and WC duct walls. While controls for temperature (at <300 °C) and hydrogen concentration in the coolant gas would be required particularly for in-vessel use, the lower weight densities and quick decay of contact dose rates compared with other candidate materials would be reasons to select these hydride shielding materials.