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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.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Latest News
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
P. L. Arnsberger, M. Mazumdar
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 140-149
Technical paper | doi.org/10.13182/NSE72-A28427
Articles are hosted by Taylor and Francis Online.
In thermal hydraulic design of nuclear reactor cores it is of interest to know the probability for 0, 1, 2, . . D hot channels and/or cladding and fuel hot spots [i.e., channels (spots) in the core at which temperature limits are exceeded]. Furthermore, it might even be advantageous to design a core for a maximum permissible number of such hot channels (spots) by comparing the safety considerations with the plant efficiency. Numerical procedures available in the open literature using statistical methods are currently restricted to the evaluation of hot channel or hot spot factors corresponding to the requirement that either the most exposed nominal channel (spot) or all channels (spots) in the entire core do not exceed imposed temperature or heat flux limits. This paper describes a method, hereafter referred to as “Method of Correlated Temperatures,” which enables an evaluation to be made of the entire probability distribution of the number of hot channels as a function of the corresponding hot channel factor. A quantitative comparison is performed between the proposed method and other procedures currently in use by applying the different methods to a hot channel factor analysis of a simplified hypothetical LMFBR-type core.