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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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.”
Shigeaki Nakagawa, Kazuhiko Kunitomi, Kazuhiro Sawa
Nuclear Technology | Volume 115 | Number 3 | September 1996 | Pages 266-280
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A15837
Articles are hosted by Taylor and Francis Online.
A modular high-temperature gas-cooled reactor (MHTGR) is expected to be one of the best energy sources in the near future because it can supply high-temperature heat and have high thermal efficiency and sufficient safety features. The safety evaluation of the future MHTGR should be performed based on the experience obtained from the safety evaluation of the High-Temperature Engineering Test Reactor (HTTR). The safety evaluation of the HTTR was performed considering the specific safety design features of the HTGR and is applicable to the future MHTGR. Before the detailed safety evaluation of the future MHTGR, the safety evaluation method and results of the HTTR should be reviewed, and newly established acceptance criteria and methods for selecting evaluation events must be clarified. This paper describes in detail the method and results of the safety evaluation of the HTTR.