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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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Fusion Science and Technology
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Optimizing nuclear plant outages: Data analytics tools and methods for enhancing resilience and efficiency
Nuclear power plant refueling outages are among the most complex phases in a plant’s operational cycle.1 During these outages, tens of thousands of activities, including maintenance and surveillance, are conducted simultaneously within a short timeframe. Typically lasting three to four weeks, these operations involve large crews of contractors with diverse skill sets performing tasks ranging from testing and surveillance to maintenance. Outages may extend longer if major backfitting or modernization projects are planned. Consequently, plant outages are expensive, incurring significant operational costs, such as contractor labor and equipment, as well as the loss of generation while the plant is off line. This can easily cost a plant operator more than $1 million a day. Therefore, there is a constant need to mitigate the economic impact on plants by reducing the frequency, duration, and risks associated with these outages.2,3
J. A. Koski, J. B. Whitley
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 789-794
Impurity Control | Proceedings of the Seveth Topical Meeting on the Technology of Fusion Energy (Reno, Nevada, June 15–19, 1986) | doi.org/10.13182/FST86-A24836
Articles are hosted by Taylor and Francis Online.
The heat flux and fluid flow conditions for a water cooled limiter tube are simulated with an electron beam heating apparatus, and the results are compared to empirical models based on existing heat transfer correlations. For the conditions of highly subcooled flow boiling in a horizontal tube subjected to a heat flux from only one side, two principal observations were noted. First, existing heat flux correlations, which were developed for use with uniform circumferential heat flux distributions, can be used to provide a good first approximation of the one-sided heat removal for the range of experimental conditions covered. Second, the peak heat flux at the tube surface predicts the onset of critical heat flux (burnout) better than the average heat flux.
