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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
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.