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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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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.”
J.M. Perlado
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 1303-1308
Fusion Application | doi.org/10.13182/FST86-A24910
Articles are hosted by Taylor and Francis Online.
The more important neutronic characteristics are simultaneously analyzed in the context of fusion-fission blankets. The analysis is referenced to a gas protected cavity, where dimensions and material compositions are varied. It is intended to know the regimes in which that hybrid blanket works when two independent variables are changed. The 6Li enrichment and the atomic density of 238U have been selected as those variables, and the study is performed for two different solid breeders Li2O and γ-LiAlO2. The effect of the thickness of the fertile zone was pointed out in previous articles and here we look for an optimum working point and will set a comparison with precedent results when LiH is used as the solid breeder. A physical figure of merit is established, which relates the characteristics of the fertile zone. Constraints on the TBR and fissile production are introduced to obtain efficient working points. Finally, the He, liquid lithium and Li17Pb83 eutectic are considered as candidate coolants and their effects on the neutronic performances are analyzed.