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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Hiroshi Kawamura
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 246-255
Technical Paper | Uranium Resource / Reactor | doi.org/10.13182/NT76-A31642
Articles are hosted by Taylor and Francis Online.
In a reactor transient analysis, the friction factor and the heat transfer coefficient are assumed equal to the steady-state values, even in a transient state. The transient turbulent flow in a circular tube subjected to a step change of pressure gradient is calculated numerically. Transient variations of the friction factor and the heat transfer coefficient are obtained. Effects of the Reynolds number and a wall heat capacity are also examined. The quasi-static momentum equation is found to be approximately valid for both accelerated and decelerated turbulent flows. The quasi-static energy equation is valid for flow transients of gas-cooled reactors.