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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
E. Rolstad, K. D. Knudsen
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 168-176
Technical Paper | Fuel | doi.org/10.13182/NT72-A31051
Articles are hosted by Taylor and Francis Online.
Fuel performance studies at the Halden reactor have given valuable information on how various design parameters affect the mechanical interaction between fuel and cladding. The experiments have also indicated how the interaction is dependent on burnup and on the actual power history of the fuel rod. This information was obtained by means of differential transformer type of detector, measuring the changes in length and diameter of fuel rods while operating at power in the reactor. Based on this experience, a simple graphical model has been proposed for the prediction of interaction between fuel and cladding as a function of power history and bumup. This concept, referred to as “iso-gap curves,” clearly demonstrates the importance of avoiding an increase in power at high burnup and could be useful when planning reactor operations with respect to fuel management schemes, i.e., power changes, control rod movement, fuel shuffling, and loading.