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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.
A. S. Bain
Nuclear Technology | Volume 3 | Number 4 | April 1967 | Pages 240-244
Technical Paper and Note | doi.org/10.13182/NT67-A27763
Articles are hosted by Taylor and Francis Online.
UO2 fuel elements, sheathed in Zircaloy or stainless steel, were irradiated under controlled conditions to study the transfer of heat across the fuel-to-sheath interface. Variables studied were diametral clearance, heat-transfer medium, duration of irradiation, and power rating. After irradiation, fractured and polished cross sections and β autoradiographs were examined to determine the temperature distribution in the UO2. The heat-transfer coefficient h increases with increasing power per unit length. For a specified power, h increased with lower initial clearances. The use of helium instead of argon increased h especially with large clearances, but by a factor much less than the ratio of the thermal conductivities of the gases. Values of h varied widely with lead-bonding; in some positions, h was very large, whereas in others its values were less than for the argon-filled elements. Metallographic examination showed that the lead had moved from some areas of the interface, leaving gaps with poor heat transfer. In the loop elements the grain-growth pattern indicated that some of the heat passed through the lead that had flowed between the pellets. Elements evacuated just before final sealing had values of h equal to or higher than those for argon-filled elements. This is tentatively attributed to the release of natural gases (mainly hydrogen) from the U02 pellets during irradiation, as observed in auxiliary experiments.