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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
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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Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Nailiang Zhuang (Univ of Michigan/Harbin Eng Univ), Kui Zhang (Univ of Michigan/Xi’an Jiao Tong Univ), Annalisa Manera, Victor Petrov (Univ of Michigan)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 250-262
Helical coil steam generators feature excellent heat transfer performance, compactness and mature manufacturing technology. In most designs, the two-phase mixture flows on the shell side of the heat exchanger, however in the steam generator design adopted in advance reactors such as the NUSCALE reactor design, the two-phase flow mixture flows in the helical coils of the heat exchanger. To improve the computational models used to predict the performance of such steam generators, it is necessary to characterize the behavior of two-phase flows in helical coils. In the present paper, detailed measurements of the void fraction distribution of an air-water two-phase flow in a glass transparent helical coil were conducted. At this aim, an X-ray radiography and high-speed videography system were used. The high-resolution measurements were also used to identify and classify flow regimes. A total of 15 runs is presented in this paper, classified into 6 flow regimes, namely: bubbly flow, plug flow, stratified wavy flow, slug flow, semi annular flow and annular flow.