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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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2024: The Year in Nuclear—April through June
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from April through May 2024.
Stay tuned for the top stories from the rest of the past year.
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.