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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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Fusion Science and Technology
Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
Balabhadra Misra, Grover D. Morgan
Fusion Science and Technology | Volume 9 | Number 3 | May 1986 | Pages 452-458
Technical Paper | Blanket Engineering | doi.org/10.13182/FST86-A24731
Articles are hosted by Taylor and Francis Online.
An assessment of the role of the design and operating parameters on the performance of solid breeder blankets based on lithium ceramics (Li2O and γ-LiAlO2) was carried out. The results indicate that not only poor thermophysical properties but also uncertainties associated with the property data base are the design-limiting f actors. In addition, the operating conditions such as the upper and the lower temperature limits, the choice of breeder materials either in the form of sintered pellets or in sphere-pac form, the interfacial contact resistance between the coolant channels and the solid breeder, and the diffusion characteristics of tritium and chemical interactions between tritium and the solid breeder play a prominent role in selection of blanket concepts. Designs to account for the expected degradation of the thermophysical properties due to thermal sintering and nuclear irradiation lead to high coolant and structural material fractions, and thus may result in a lower tritium breeding ratio. The results of the parametric studies show that water-cooled solid breeder blanket designs require a firmer data base for the operating temperature limits, the thermophysical properties, the gap conductances, and the tritium retention and release characteristics of solid breeders.