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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.”
Ezio Bittoni, Marcel Haegi
Fusion Science and Technology | Volume 18 | Number 3 | November 1990 | Pages 373-383
Alpha Particles in Fusion Research | Technical Paper | doi.org/10.13182/FST90-A29270
Articles are hosted by Taylor and Francis Online.
Calculation of alpha-particle confinement by a guiding center orbit-following numerical code requires the computation of very long particle trajectories. Due to their enormous length, these computations are subject to the possible accumulation of small errors, and the alpha-particle population is usually extrapolated from a single-particle history for every point of the initial parameter space. To overcome these difficulties, a numerical diffusion coefficient is derived for each point of the initial parameter space by averaging over a certain number of single-particle histories for each point of this space. This method has been applied to fast-alpha-particle confinement of the Next European Torus benchmark and the numerically derived diffusion coefficients are compared with analytical expressions from theoretical models.