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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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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.
Duk Jin Kim, Jong Hyun Kim, K. F. Barry, Ho-Young Kwak
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 337-351
Technical Paper | Fission Reactors | doi.org/10.13182/NT11-A13312
Articles are hosted by Taylor and Francis Online.
Thermoeconomic analysis was performed for high-temperature gas-cooled reactors (HTGRs) coupled with a steam methane reforming (SMR) plant in order to estimate the hydrogen production cost. Two possible HTGRs, a modified Brayton cycle HTGR (GT-HTGR) coupled with an SMR plant and a modified steam cycle HTGR (SC-HTGR) coupled with an SMR plant, were considered in this study. In these analyses, mass and energy conservation were applied strictly to each component of the system. Also, quantitative balances of the exergy and the exergetic cost for each component and for the whole system were carefully considered. The hydrogen production cost was estimated to be about $0.825/kg [$7.25/one million Btu (MM Btu)] for the GT-HTGR-SMR system and $0.728/kg ($6.41/MM Btu) for the ST-HTGR-SRM system with a uranium fuel cost of $8.40/MWh. The hydrogen production cost estimated in this study is considerably less than the economic target of $1.70/kg ($14.96/MM Btu), indicating that hydrogen production using HTGR with an SMR plant has great economic potential.