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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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.”
S. Locke Bogart, John A. Dalessandro (EASI), Peter Koert (IRT), Thomas J. Seed (LANL), Daniel L. Vrable (GAT), Carl E. Wagner (TRW), Carl F. Weggel (EASI)
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1339-1344
Next-Generation Device | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A39954
Articles are hosted by Taylor and Francis Online.
The Demountable Tokamak Fusion Core (DTFC) concept is a water-cooled, normally conducting tokamak provided with joints in the toroidal field coil turns. These joints, located in the top and bottom horizontal members of each turn, permit the removal and replacement of the core of the tokamak (central OH coil, vacuum vessel, impurity control system, RF heating and current drive systems, inner blanket, and PF trimming coils). The rest of the tokamak (outer blanket, toroidal field current return coils, and main PF coils) remains in-place. This feature arises because the DTFC was conceived in recognition of the fact the core of the tokamak is directly exposed to fusion neutron and charged particle radiation and is the subsystem that will fail first. Provision for the replacement of the core in a straightforward way will significantly increase the availability of a DTFC facility for engineering and commercial applications.