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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.
T. B. Burley, M. D. Freshley
Nuclear Technology | Volume 9 | Number 2 | August 1970 | Pages 233-241
Fuel | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28812
Articles are hosted by Taylor and Francis Online.
Plenum gas temperature and internal gas pressure buildup were measured during irradiation in four vibrationally compacted UO2-2 wt% PuO2 fuel rods. Two each of the four instrumented fuel rods operated to peak burnups of 9900 and 6000 MWd/ MTM, respectively. Experimental results indicate that sorbed gases and moisture released from the fuel react rapidly with the Zircaloy cladding and do not contribute to the internal pressure. The predominant modes of fission gas release from high and lower power fuel rods is different. The rates of pressure buildup in the high and low burnup fuel rods, which correspond to about 34 and 12% fission gas release, respectively, were consistent with fuel temperature-dependent fission gas release fractions predicted from postirradiation gas collection data obtained from similar fuel rods. Measured plenum gas temperatures during irradiation varied directly with coolant outlet temperature.
