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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. A. Strehlow, H. C. Savage
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 127-137
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16282
Articles are hosted by Taylor and Francis Online.
The permeation and the pressure dependence of the permeation of hydrogen isotopes through metals and oxidized metals were studied at temperatures from 300 to 800°C and at pressures of 10-3 Torr to 1 atm. Such knowledge is important to tritium management in both fusion and fission nuclear reactors. An adequate basis for predicting the permeation of hydrogen at very low pressures has not previously been established; therefore, the two complementary objectives of this study were (a) to determine the pressure dependence of hydrogen permeation through materials of which steam generators might be built, and (b) to determine whether an oxide film might serve as a tritium permeation barrier. The metals studied included nickel, Type-304 L stainless steel, Hastelloy N, Incoloy 800, Croloy T9, Croloy T22, and Type-406 stainless steel. Deuterium, rather than normal hydrogen, was used as the permeating gas in order to achieve high sensitivity in the mass spectrometric analyses. At a given temperature, the permeation rate of deuterium through metals that are substantially free of oxide films was found to proceed with a half-power pressure dependence in accordance with the relationship
where J is the permeation flow rate, K is a constant, and P1 and P2 are the upstream and downstream gas pressures, respectively.