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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
Helmut Elbel, José LóPez Jiménez
Nuclear Technology | Volume 43 | Number 1 | April 1979 | Pages 88-99
Technical Paper | Fuel | doi.org/10.13182/NT79-A16177
Articles are hosted by Taylor and Francis Online.
The heat transfer coefficient of the interface between the fuel and the cladding of fast reactor fuel rods with different burnups was derived through the analysis of the structure of the UO2-PUO2 fuel A decrease of the heat transfer with increasing burn-up was found, resulting in rising fuel surface temperatures. The predictions of a theoretical heat transfer model agreed well with the experimental result. The deterioration of the heat transfer could be explained by fission gas release into the residual gap between fuel and cladding. Heat transfer through contact spots played a negligible role due to low contact pressure and very early formation of an oxide layer on the cladding.