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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
M. Wadle
Nuclear Science and Engineering | Volume 100 | Number 2 | October 1988 | Pages 89-104
Technical Paper | doi.org/10.13182/NSE88-A29019
Articles are hosted by Taylor and Francis Online.
Experimental data are compared to calculations with a one-dimensional computer code (DUESE). In a systematic study, two-phase flow models (homogeneous and drift-flux) and empirical parameters in constitutive correlations of different code versions were tested. Special attention was given to the pressure rise in the diffuser, which could be calculated adequately only with the drift-flux correlation taken from the SOLA-DF code., Velocity data for choked flow conditions are compared to four different two-phase sound velocity models, which give the best agreement with the equilibrium sound velocity.