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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.”
Cheol Shin Lee, Chan Eok Park, Chul Jin Choi, Jong Tae Seo
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 42-49
Technical Note | doi.org/10.13182/NT02-A3302
Articles are hosted by Taylor and Francis Online.
The Korean Standard Nuclear Power Plant (KSNP) has adopted the digital plant protection system (PPS) to enhance the reliability and safety of the plant. Although the digital PPS can be designed with high reliability, it is considered to be vulnerable to common mode failure (CMF) in the system software, resulting in a total loss of the built-in hardware redundancy. Therefore, a comprehensive evaluation has been performed to demonstrate the intrinsic capability of the KSNP design in coping with the design-basis events concurrent with CMF in the digital PPS. Instead of the conservative bounding analysis methodology, a best-estimate analysis methodology has been developed and utilized since the design-basis events accompanied by CMF in the digital PPS are categorized as beyond-design-basis events. An additional reactor trip function on high containment pressure in the diverse protection system (DPS), which is totally diverse from the PPS and is not affected by the CMF in the digital PPS, has been proposed to meet the acceptance criteria of the evaluation results. A variety of diverse means such as the DPS, process control systems, and operator actions including design modification have been verified to be effective in mitigating the design-basis events with CMF in the digital PPS.