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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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.