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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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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.
R. L. Klueh
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 287-296
Technical Paper | Material | doi.org/10.13182/NT75-A24430
Articles are hosted by Taylor and Francis Online.
Several investigators have demonstrated empirical relationships between creep and rupture properties for various metals and alloys. We have examined empirical relationships between the rupture life and the minimum creep rate and the time to the end of steady-state creep (start of tertiary creep) for four heats of normalized-and-tempered Cr—1 Mo steel with different carbon contents. The primary objective was the determination of the conditions that affect the correlation. The following relationships were obeyed: andt2 = Fs tr , where t2 is the time to start tertiary creep, tr is the rupture life, is the steady-state creep rate, and C and Fs are constants. The primary micro-structural constituent (proeutectoid ferrite or bainite) of the matrix and the precipitates present in that matrix (before test or formed during test) played a significant role in the correlation of the data with the empirical relationships.