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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
Andr Preumont
Nuclear Technology | Volume 58 | Number 3 | September 1982 | Pages 483-491
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32982
Articles are hosted by Taylor and Francis Online.
Received July 30, 1980 Accepted for Publication March 10, 1982 The results of a study on the vibrational behavior of pressurized water reactor (PWR) fuel rods are presented. It is shown that a linear finite element model is representative for the low amplitude vibrations. A parametric study on the pellet diameter and the plenum spring force suggests that the vibrational behavior should be expected to change with irradiation. The amount of this change, however, can hardly be estimated from the very limited available experimental data. A typical PWR clad-to-grid connection is analyzed in detail from the point of view of vibratory wear. A procedure is presented to compute a minimum grid spring force consistent with the maximum allowed vibration amplitude.