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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.
V. Subramanian, R. Baskaran, J. Misra, R. Indira
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 83-92
Reactor Safety | doi.org/10.13182/NT11-A12544
Articles are hosted by Taylor and Francis Online.
In core disruptive accident conditions of sodium-cooled fast reactors, the reactor containment building (RCB) is filled with a large amount of sodium aerosols, along with fuel and fission product aerosols. The environmental source term depends on the quantity of aerosols released from RCB, which in turn depends on the quantity of aerosols that remains suspended in the RCB volume. The sodium aerosols are generated by the combustion process, resulting in micrometer-sized aerosols, while fuel and fission product aerosols are generated by vaporization condensation, resulting in nanometer-sized aerosols. To ascertain the behavior of mixed aerosols generated by the different processes, experiments are conducted by generating sodium aerosols and nonradioactive fission product aerosols and then studying their behavior in a closed vessel. The study includes (a) the initial size distribution of CeO2 and SrO2 aerosols, (b) the behavior of suspended mass concentration as a function of time, and (c) the behavior of suspended number concentration as a function of time. The initial size of the sodium combustion aerosols is [approximately]1.0 m, whereas the initial size of the fuel and fission product aerosols is nanometer sized ([approximately]30 nm). In the context of the behavior of the two different-sized aerosols, sodium aerosol behavior dominates the overall suspended mass concentration of the system. The rate of change of number concentration exhibits two regions. The timescale involved for the Brownian coagulation region is found to be [approximately]80 min for nonradioactive fission product aerosols, whereas it lasts only 20 to 30 min when the aerosol system is mixed with sodium aerosols.