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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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2024 ANS Annual Conference
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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.
Marie-Sophie Chenaud, Gilles Rodriguez (CEA), Jean-François Dirat, Alexandre Villedieu (Framatome)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 562-570
Design studies of the ASTRID nuclear island are conducted in accordance with GEN IV reactors criteria, in particularly for safety and operability improvement.
The latest configuration of ASTRID nuclear island (including primary and secondary circuits) has been produced by Framatome at the end of 2017 corresponding to the middle of the Basic Design phase.
This paper describes the main ASTRID safety and operational requirements and the up-to-date design options, focusing on innovative options. Items addressed in the paper include: vessels (main and safety vessels), core support structures, primary pumps and pumps-diagrid connecting pipes, Above Core Structure, Intermediate Heat eXchangers, internal vessel, upper closures (slab and rotating plugs), Decay Heat Removal systems and core catcher. The global architecture of the primary and secondary circuits, in connection with the Gas Power Conversion System, is also presented.
This paper reports on the progress of the studies concerning:
- thermal hydraulics and thermal mechanics,
- evaluations of the seismic resistance,
- in-service inspection,
- qualification needs.
Lastly, it indicates the open options for materials, components and general architecture, which will continue to be studied in the second half of the Basic Design phase.