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Division Spotlight
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.
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.”
Hisashi Sagawa, Hiroshi Kawamura, Yoshiaki Ikejima, Naoki Imaizumi, Rokuro Oyamada, Kuniaki Miura
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 732-735
Tritium Processing | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30491
Articles are hosted by Taylor and Francis Online.
A breeder blanket, whose purposes are to breed tritium and to produce thermal energy, is indispensable for a fusion reactor. In addition to demonstrating the physics of burning D-T plasmas, an experimental reactor such as the ITER will also conduct a verification test of a blanket design. An in-pile functional test has been considered to obtain above engineering data since 1992 in the JMTR project. The sweep gas system which is a system to measure and recover the tritium released from a blanket mock-up has been designed. From the results of the design, the sweep gas system will be sufficient for the in-pile functional test in the JMTR.