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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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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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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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.”
L.L. Lengyel, K. Borrass
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1760-1765
Plasma Heating, Impurity Control, and Fueling | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40015
Articles are hosted by Taylor and Francis Online.
The fueling requirements of fusion reactors are analyzed on the basis of a recent assessment performed for NET (Next European Torus). Results of penetration depth calculations applied to single pellets under thermonuclear plasma conditions are described. Data corresponding to the commonly used neutral gas shielding ablation model and a magnetic shielding approximation are compared. The pellet size and pellet velocity requirements for central fueling are established. Scenario calculations are performed with the help of a 1D tokamak transport code. The pellet size, pellet velocity, and injection frequency requirements for continuous fueling or, for example, ignition with the help of pellets are obtained. The effect of runaway electrons, NB ions and alpha particles is estimated by calculating the ablation rates caused by these particles in fusion plasmas and comparing them with the ablation rate induced by thermal electrons.