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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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May 2025
Latest News
DTE Energy studying uprate at Fermi-2, considers Fermi-3’s prospects
DTE Energy, the owner of Fermi nuclear power plant in Michigan, is considering an extended uprate for Unit 2 that would increase its 1,100-MW generation capacity by 150 MW.
Benjamin M. Ma
Nuclear Science and Engineering | Volume 26 | Number 1 | September 1966 | Pages 99-109
Technical Paper | doi.org/10.13182/NSE66-A17192
Articles are hosted by Taylor and Francis Online.
The strain rates, strains, and stresses resulting from irradiation growth and swelling in long cylindrical solid fuel elements in unsteady-state conditions are determined analytically. From the simple diffusion equation for nonequilibrium reactor system, an exact solution for neutron flux distribution is expressed by products of Bess el function with exponential time function. From the heat conduction equation with an internal heat source in unsteady state, a solution for temperature distribution in the fuel elements is obtained. A physico-mechanical analysis for the fuel elements is carried out with some basic assumptions concerning the properties, fabrication, end and yield conditions of the fuel, and cladding materials., The figures show the combined effects of radiation growth, swelling, and time on the components of the strain rate, strain, and stress produced in the fuel elements during reactor operation. The results are based on the derived equations and the calculated results of a numerical example.