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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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Nuclear Science and Engineering
August 2024
Nuclear Technology
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.”
Jay F. Benesch, Roger D. Bengtson, George L. Cardwell, Stephen A. Eckstrand, Rex F. Gandy, Paul Wildi
Fusion Science and Technology | Volume 2 | Number 3 | July 1982 | Pages 398-409
Technical Paper | Special Section Contents / Experimental Devices | doi.org/10.13182/FST82-A20772
Articles are hosted by Taylor and Francis Online.
The PRETEXT tokamak was designed to investigate the initial stages of a tokamak discharge. The machine has a major radius of 53 cm, limiter radius of 15 cm, and a toroidal field (TF) of 8 kG. Plasma currents of 40 to 60 kA with durations of 40 to 70 ms are typical. Chord average density is of the order of 1013 cm−3, the electron temperature Te(0) ∼ 300 eV, and the effective charge Zeff ∼ 3. The ohmic-heating (OH) transformer is unique among operating machines, having an iron core and air return. Combinations of mechanical and electronic switches in the OH and TF power supplies provide good reliability at low jitter and low cost. The design and construction of the PRETEXT tokamak are discussed in enough detail to give a feeling for the compromises that must be made and the problems that will be encountered in the building of any controlled thermonuclear reactor device.