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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.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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.
Krishna Vinjamuri, Richard R. Hobbins
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 145-150
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33213
Articles are hosted by Taylor and Francis Online.
A postirradiation examination of two uranium aluminide (UAlx) fuel plates from the Advanced Test Reactor (ATR) was conducted. The two fuel plates failed due to pinhole corrosion during irradiation to ∼76% of the maximum burnup limit of 2.3 X 1021 fission/cm3. It is believed that the aluminum cladding failed due to pit corrosion initiated at an existing pit ∼0.0076 to 0.0102 cm (3 to 4 mil) deep at a hot spot. About 0.2 and 0.8 g of UAlx fuel was washed out of these plates through the pinholes due to aqueous corrosion and erosion of the UAlx under ATR primary coolant conditions. Aluminum cladding pit corrosion depth and UAlx fuel corrosion-erosion mass rates under the ATR primary coolant conditions were calculated to be 0.23 cm/yr and 14 g/yr, respectively.