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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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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.”
O.K. Kveton, R.S. Matsugu, S.K. Sood
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1541-1546
Inertial Fusion Reactor Studies | doi.org/10.13182/FST92-A29939
Articles are hosted by Taylor and Francis Online.
Two separate conceptual designs of commercial fusion power plants have been developed for the U.S. Department of Energy. Inertial confinement reactor designs based on the driver systems of the KrF excimer gas laser and the heavy ion linac were developed and analyzed. The preliminary system design for reactor exhaust gas recovery and purification for tritium processing is described. The integrated design consists of a palladium-silver permeator for impurity removal, a high temperature isotope exchange reactor for impurity processing, pressure swing adsorption for tritium recovery from helium and water distillation and cryogenic distillation for isotope separation. A comparison between inertial fusion and magnetic fusion tritium systems is presented.