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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
M. Schad
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 267-288
Technical Paper | Material | doi.org/10.13182/NT80-A32530
Articles are hosted by Taylor and Francis Online.
We investigated whether it is possible to predict corrosion effects for austenitic steels exposed to liquid sodium with an analytical diffusion model The comparison between experimental measurements of corrosion and calculated corrosion effects is described. A diffusion model served as the basis for the calculations. The comparison showed that the analytical model is able to predict the corrosion effects. The diffusion model is based on the observed sodium corrosion characteristics. It includes the upstream history of the sodium as well as the influence of the corroding wall at the considered location. The test loop’s maximum and minimum sodium temperatures were 750°C (1388°F) and 150°C (303°F = cold trap temperature corresponding to 2 to 3 ppm oxygen content), respectively. The cold trap was part of the main circuit. The loop was built of steel 1.4571. The samples were made of steel 1.4571 or 1.4488. The metallographic investigated surfaces were exposed to sodium at temperatures of 500°C (933°F) to 750°C (1383°F) in the heated part of the loop. The comparison between experimental and analytical results shows that the model is able to predict most characteristics of the sodium austenitic corrosion. The analytical results are qualitatively correct and to a fairly good degree quantatively accurate as well. The accuracy of the model predictions depends primarily on the degree of knowledge of the factors determining the diffusion such as the sodium saturation limits and the diffusion coefficient of the individual stainless-steel elements in the corroding wall.