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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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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
Andreas Pritzker, Jrg Gassmann
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 289-297
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32475
Articles are hosted by Taylor and Francis Online.
A method has been developed that is based on simplified reliability models and that allows us to estimate the risk of nuclide release from underground nuclear waste repositories. The prototype repository is treated as a combination of geological and man-made barriers. Risk depends on time and is expressed as failure probability of the barrier system for all possible initiating events, multiplied by the inventory to be released. The results include, for each nuclide, the time and amount of the maximum probable discharge rate, which can be used in a biosphere transport model. They also illustrate the effectiveness of single barriers in the barrier system, and therefore allow a preselection among alternative barrier concepts, barrier qualities, and repository sites. The probabilistic failure models for the single barriers and the entire barrier system depend on only a few parameters; therefore, the application of the method is fast and inexpensive. It has to be stressed, however, that this simple method cannot replace more detailed and sophisticated risk studies, but allows concentrating them on preselected repository concepts. It therefore represents a useful tool in the early design and site evaluation phase for all kinds of repositories and waste types. Its usefulness has been demonstrated by performing several case studies with the computer program WRISK on some typical nuclides in high level waste, bearing in mind that for a repository concept all nuclides of possible importance should be considered.