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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
NRC issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
Justin D. Talley, Seungjin Kim, Tangwen Guo, Gunol Kojasoy
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 2-12
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT167-2
Articles are hosted by Taylor and Francis Online.
The present study investigates the geometric effects of a 45-deg elbow on the development and distribution of local two-phase flow parameters in horizontal bubbly flow. A round pipe with an inner diameter of 50.3 mm is used as a test section throughout the study. The test section consists of a 90-deg elbow followed farther downstream by a 45-deg elbow. Local two-phase flow parameters and pressure measurements are made at three different axial locations, one upstream and two downstream of the 45-deg elbow. In total, 15 different flow conditions are investigated for the present analysis. At the measurement port just downstream of the 45-deg elbow, the local parameters are acquired in both the vertical and horizontal directions along the radius of the pipe cross section to capture geometric effects of the flow restriction. The local two-phase flow parameters acquired in the present study include void fraction, bubble velocity, interfacial area concentration, and Sauter mean diameter. In view of one-dimensional transport, the local void fraction and interfacial area concentration are area averaged and plotted along the axial direction. The characteristic geometric effects of the flow restrictions are clearly demonstrated in the distribution of the two-phase flow parameters and pressure, as well as their development along the flow direction. The drastic changes in the interfacial area concentration across the elbow suggest that a 45-deg elbow induces significant changes in bubble interaction mechanisms.