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Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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.
Tim D. Bohm, Laila El-Guebaly, ARIES Team
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 278-282
In-Vessel Components - FW, Blanket, Shield & VV | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12365
Articles are hosted by Taylor and Francis Online.
In ARIES tokamak designs, there are assembly gaps between adjacent blanket and shield modules. These gaps allow increased levels of radiation to reach outer components. Three-dimensional models of the tokamak were used to analyze the effect of radiation streaming through both straight and stepped gaps of 1 cm and 2 cm wide. We proposed a novel idea of inserting a WC shield block within the double step region to further attenuate the streaming neutrons. Radiation damage parameters were calculated for the inboard components including the first wall, shield, manifolds, vacuum vessel, and magnet. Our results show that straight gaps allow too much radiation to reach the inboard components, resulting in large peaking in radiation damage parameters. The double stepped gap with WC shield block show reduced peaking and are effective at protecting the vacuum vessel and magnet.