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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.
Aleksandra Czyrska-Filemonowicz, Philip J. Ennis
Nuclear Technology | Volume 66 | Number 1 | July 1984 | Pages 149-157
B. Structural Characterization of Microstructure and Matallographical Aspect | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33463
Articles are hosted by Taylor and Francis Online.
The effect of carburization on the impact strength and microstructure of the commercial Fe-32 Ni-20 Cr alloy 800H has been investigated in the 20 to 800°C temperature range. The properties and microstructure of test pieces carburized at 850°C for up to 500 h in an argon-10 vol% methane atmosphere and of specimens heat treated at 850°C in an inert atmosphere for the same times were compared. The results showed that aging at 850°C reduced the impact strength at 20 to 800°C. With an increasing degree of carburization, the impact strength was progressively reduced to ∼50 J at a bulk carbon content of 0.6 wt%. Heat treatment after carburization caused a further decrease in impact strength as the depth of carbon penetration increased. Microstructural examination by optical and transmission electron microscopy (TEM) of broken test specimens showed precipitation of M23C6 carbides on grain and twin boundaries and intragranular fine precipitation of TiC and M23C6 as well as the presence of primary titanium carbonitrides. The TEM investigations using extraction replica and thin foil techniques established that the M23C6 carbides at grain boundaries retained a crystallographic orientation to one grain and grew into the adjacent grain. Lamellae of M23C6 carbides precipitated on noncoherent twin boundaries grew into the grain parallel to the twin plane, whereas M23C6 on coherent twin planes grew as plates along the twinning plane.