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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.”
H. C. Mantz, D. A. Bowers, F. R. Williams, J. W. Sapp, M. A. Witten
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1133-1137
Ignition Device | doi.org/10.13182/FST91-A29495
Articles are hosted by Taylor and Francis Online.
The purpose of the inboard limiter of the Compact Ignition Tokamak (CIT) is to protect the vacuum vessel from high heat loads during operation. The limiter components must be maintained remotely; therefore, they must be designed to reduce maintenance time as much as possible. This drives the design toward larger tiles to reduce the number of items to be replaced; however, other factors drive the design toward smaller tiles. The thickness of the tiles must also be as small as possible to reduce overall build of the distance from the inner magnet leg to the plasma. This paper presents the factors involved in sizing of the tiles and shows design concepts for several sizes of tiles. It also discusses the material development that has been accomplished to date and the development in work to increase the thermal conductivity and strength of carbon-carbon materials for use as the limiter material.