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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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
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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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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.
P. C. Hall, R. B. Duffey
Nuclear Science and Engineering | Volume 58 | Number 1 | September 1975 | Pages 1-20
Technical Paper | doi.org/10.13182/NSE75-A26763
Articles are hosted by Taylor and Francis Online.
In postulated loss-of-coolant accidents in water-cooled reactors, it is possible for an increase in Zircaloy clad temperature, coupled with reactor depressurization, to give significant local clad strain, and hence reduced area for coolant flow. This paper establishes a simple method of calculating the effect of consequent impairment of local heat-removal capability. An existing flow model, due to Gambill, has been used to estimate the local reduction in the heat transfer coefficient due to clad ballooning. By formulating an energy balance for the fuel pins, temperature transient curves for the distorted cladding are derived from those for undistorted fuel.To analyze the complicated two-phase phenomena, several simplifying assumptions are contained in the flow model. Results, therefore, are given for a range of flow and blockage assumptions, and are shown to be in reasonable accord with an analysis using large and complex computer codes and with all available experimental data.The model can be applied to all types of water-cooled reactors, including pressure tube reactors, by a suitable evaluation of the resistance to bypass flow.