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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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Prepare for the 2025 PE Exam with ANS guides
The next opportunity to earn professional engineer (PE) licensure in nuclear engineering is this fall. Now is the time to sign up and begin studying with the help of materials like the online module program offered by the American Nuclear Society.
Katsuhiro Ohkawa, Richard T. Lahey, Jr.
Nuclear Technology | Volume 67 | Number 3 | December 1984 | Pages 437-451
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33501
Articles are hosted by Taylor and Francis Online.
A gamma-ray scattering densitometer was developed for the nonintrusive measurement of the local void fraction in complex geometries. The densitometer system consisted of a shielded 137Cs photon source, a NaI photon detector, and a collimator system that defined the scattering volume within which the photons were scattered. An analytical model for the scattering events was developed. This model took the form of an integral equation, which expressed the measured counting rate in terms of the geometric configuration, local density, and the nuclear properties of the scattering volume. An interactive-graphics-based numerical procedure for inversion of the integral equation was developed. Results of two-phase flow measurements in a concentric annulus are given.