ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
W. Van Witzenburg, L. G. J. Janssen, J. Prij
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 184-187
Technical Note | Reactor | doi.org/10.13182/NT77-A31862
Articles are hosted by Taylor and Francis Online.
By using the finite-strain theory, an effective temperature, defined as a uniform temperature producing the same deformation rates as the actual temperature gradient, of a thick-walled internally pressurized closed-end tube with an over-the-wall radial temperature gradient, is expressed in terms of original tube geometry, strain, temperature distribution, and creep properties of the tube material. For a stainless-steel cladding tube of a fission reactor fuel pin, with a radial temperature gradient of 50°C over the wall, the effective temperature equals the average of the instantaneous inner and outer surface temperatures to within 1°C.