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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.
Constantine P. Tzanos
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 181-190
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3524
Articles are hosted by Taylor and Francis Online.
Benchmark experiments simulating flows in a pressurized water reactor rod bundle were analyzed to evaluate the performance of a state-of-the-art computational fluid dynamics (CFD) code. For the simulation of turbulence a number of standard k-[curly epsilon] models were used. Away from components that cause significant flow deflections, the difference between mean velocity predictions and measurements is within the experimental error. Near such components there is significant discrepancy between velocity predictions and measurements. Even in rod bundles without flow deflectors, the turbulence predictions of standard k-[curly epsilon] models show significant discrepancy with measurements. These discrepancies are greater near components that cause flow deflections. Turbulence generated by vanes on spacer grids significantly enhances thermal mixing. To improve the fidelity of CFD simulations of flows in reactor rod bundles, the development of Reynolds averaging of the Navier-Stokes equations turbulence models based on such flows is needed.