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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.”
Chun-Sheng Chien, Shih-Jen Wang, Show-Chyuan Chiang
Nuclear Technology | Volume 161 | Number 3 | March 2008 | Pages 203-209
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3923
Articles are hosted by Taylor and Francis Online.
The MAAP4 code is a fast-running severe accident analysis and management code widely used in nuclear industrial applications. It has been used as a severe accident analysis tool with which the timing of key events and source terms in the accident are assessed in Taiwan for many years. In the case of a loss-of-coolant accident (LOCA), it needs to know its break area and break elevation prior to reconstructing the accident for further analysis. For the system with more than one unknown parameter, it is not easy to identify these parameters since their tuning work becomes sophisticated.The purpose of this paper is to find a better solution for this problem by coupling an optimization module with the MAAP4 simulation code. In this paper, a recirculation line break LOCA of the Kuosheng nuclear power plant is cited as a reference case. Different recirculation line break areas are tested and verified. This optimization module coupled with the MAAP4 code can be used to identify the break elevation and area if the shroud water level drops below the break point.