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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.
Shengyao Ding, Kun Xu, Xiaojian Huang, Zheng Wang
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 350-357
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT06-A3767
Articles are hosted by Taylor and Francis Online.
This paper describes a new system for monitoring leaks in a steam generator. The new system extends the traditional 16N monitor to detect both the rate and the location of a leak. Because the transit time is different for radioactive 16N and 19O to travel from the reactor core via the hot bottom side, cold bottom side, or bend region of the U-tube in a steam generator to the gamma-ray detector, the new system uses the different transit times to identify the location of leaks. Specifically, the ratio S0 of 16N to 19O activities in the reactor core of a swimming pool reactor was calculated by combining the cross sections np(E) and n(E) with the neutron spectra n(E). The ratio S1 of 16N to 19O activities in the measurement room was also calculated and measured by the high-purity germanium and NaI(Tl) detectors. The result of the calculation agrees with the measurement within an acceptable range.