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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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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Fusion Science and Technology
February 2024
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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.
Jennifer Lyons, Edward Love, Kim Burns
Fusion Science and Technology | Volume 71 | Number 4 | May 2017 | Pages 616-621
Technical Note | doi.org/10.1080/15361055.2017.1290944
Articles are hosted by Taylor and Francis Online.
TEACUP (Tritium Effluent Analysis and Core-follow, Up-to-date and Predictive) is a tritium management and supplemental core follow program that allows its users to account for reactor coolant system (RCS) tritium sources, generate discharge release estimates, account for downstream river flows and concentrations, and calculate corresponding uncertainties. The program incorporates water balance methodologies, tritium production estimates from secondary startup neutron sources, soluble boron content, reactor coolant system tritium measurements, and seasonal river flow estimates. TEACUP was designed specifically to facilitate the tracking of Tritium Producing Burnable Absorber Rod (TPBAR) permeation since measuring in-reactor permeation directly is not feasible and prediction methodologies have thus far been insufficient. A number of models, calculations, and correlations were developed in order to quantify all of the leading sources and losses of tritium in the RCS. By comparing all of the known contributors and discharges from the RCS tritium inventory to the measured RCS tritium concentration, the unaccounted for balance (within some band of uncertainty) can be attributed to TPBAR permeation. The tritium release estimates to the river generated from TEACUP are validated by comparing them to the measured tritium releases which match well and give confidence that TEACUP is tracking and accounting for tritium appropriately. An additional check on the methodologies within TEACUP is that the cycle-to-cycle trends for tritium permeation per TPBAR are consistent in behavior and the estimated release per TPBAR across each cycle is the same within their uncertainty.