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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.
R. A. Borrelli, Joonhang Ahn, Yongsoo Hwang
Nuclear Technology | Volume 197 | Number 3 | March 2017 | Pages 248-264
Technical Paper | doi.org/10.1080/00295450.2016.1273713
Articles are hosted by Taylor and Francis Online.
Many nations are expanding or initiating nuclear energy programs as part of a national energy portfolio. Transitioning to advanced nuclear energy systems improves sustainability and promotes energy independence. These advanced nuclear energy systems also must be shown to enhance safety, safeguards, and security in order to be realistically deployed. This is of particular concern to non–nuclear weapons states, to assure compliance with International Atomic Energy Agency treaty obligations. Consequently, the relatively new research area of safeguardability addresses how to integrate goals for safety, safeguards, and security as part of a design strategy for an advanced fuel cycle. This paper presents an overall set of principles that form the foundation of a comprehensive safeguardability methodology, including the quantitative modeling studies derived therein. Results show an approach for characterizing used fuel, functional components to engineering design for nuclear materials handling facilities, and repository analysis. We conclude with an argument for the necessity of an integrative, systems assessment approach to the safeguardability of an advanced fuel cycle.