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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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.
W. T. Shmayda, A. Bruggeman, J. Braet, S. Vanderbiesen
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 721-725
Decontamination and Waste | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22681
Articles are hosted by Taylor and Francis Online.
Studie Centrum voor Kernenergie•Centre d'Etude de l'Energie Nucleaire (SCK•CEN) plans to dispose of 178 liters of tritiated solvent at their facility using a novel processing technology to oxidize the solvent. Kinectrics Inc. will assist SCK•CEN by providing tritium-management consulting support and the equipment to oxidize the solvent and capture the product water. The solvent containers have been removed from their overpacks and stored in a ventilated metal cabinet in preparation for processing. Samples have been taken from each vessel to determine liquid activity and composition. A series of cold commissioning tests have been completed to assure authorities at SCK•CEN that safe handling and destruction of the solvents is possible and that emissions during processing can be maintained at negligible levels. A series of hot commissioning tests using feedstock samples have been completed. This paper outlines the process and handling infrastructure and summarizes results from the commissioning tests.