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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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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
Glen R. Edwards, Kent A. Jones, Steven F. Halvorson
Fusion Science and Technology | Volume 10 | Number 2 | September 1986 | Pages 243-252
Technical Paper | Blanket Engineering | doi.org/10.13182/FST86-A24976
Articles are hosted by Taylor and Francis Online.
Recent inertial confinement fusion reactor designs utilize liquid 17Li-83Pb blankets to absorb the neutron and thermal fluxes. One of the crucial concerns of these designs is the compatibility of structural alloys with this lithium-lead alloy, especially because of this liquid's possible propensity for embrittling materials. Current candidate pressure vessel steels for liquid lithium or lithium-lead containment are the Cr-Mo steels such as HT-9 (12 Cr-1 Mo), 2.25 Cr-1 Mo, and niobium-stabilized 2.25 Cr-1 Mo. This investigation was therefore aimed at characterizing the lithium-lead embrittlement susceptibility of the weldments of these steels subjected to a 17Li-83Pb liquid. Results of these embrittlement studies have shown that as-welded heat-affected zones of low phosphorus and sulfur 2.25 Cr-1 Mo, niobium-stabilized 2.25 Cr-1 Mo, and HT-9 steels all exhibit liquid-metal-induced embrittlement susceptibility when subjected to a 17Li-83Pb liquid. The embrittlement, however, was found to be very dependent on post-weld heat treatment. Normally extensive post-weld heat treatments greatly ameliorate the 17Li-83Pb embrittlement, rendering these steels acceptable for 17Li-83Pb containment.