Probabilistic Safety Assessment for Instrumentation and Control Systems in Nuclear Power Plants: An Overview

Lu, Lixuan; Jiang, Jin

doi:10.1080/18811248.2004.9715491

Cited by 12 publications

(4 citation statements)

References 16 publications

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“…In the domain of NPPs, PSA is the most extensively employed method for risk assessment. In 1975, the U.S. NRC officially published the first formal report, known as WASH-1400, on PSA [106]. Subsequently, in 1981, the International Atomic Energy Agency (IAEA) released the fault tree handbook [107], marking the widespread adoption of PSA for safety evaluations.…”

Section: Traditional Risk Assessment Methodsmentioning

confidence: 99%

Emergency Decision Support Techniques for Nuclear Power Plants: Current State, Challenges, and Future Trends

Xiao,

Liang,

Tong

et al. 2024

Energies

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Emergency decision support techniques play an important role in complex and safety-critical systems such as nuclear power plants (NPPs). Emergency decision-making is not a single method but a framework comprising a combination of various technologies. This paper presents a review of various methods for emergency decision support systems in NPPs. We first discuss the theoretical foundations of nuclear power plant emergency decision support technologies. Based on this exposition, the key technologies of emergency decision support systems in NPPs are presented, including training operators in emergency management, risk assessment, fault detection and diagnosis, multi-criteria decision support, and accident consequence assessment. The principles, application, and comparative analysis of these methods are systematically described. Additionally, we present an overview of emergency decision support systems in NPPs across different countries and feature profiles of prominent systems like the Real-Time Online Decision Support System for Nuclear Emergencies (RODOS), the Accident Reporting and Guiding Operational System (ARGOS), and the Decision Support Tool for Severe Accidents (Severa). Then, the existing challenges and issues in this field are summarized, including the need for better integration of risk assessment, methods to enhance education and training, the acceleration of simulation calculations, the application of large language models, and international cooperation. Finally, we propose a new decision support system that integrates Level 1, 2, and 3 probabilistic safety assessment for emergency management in NPPs.

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Section: Traditional Risk Assessment Methodsmentioning

confidence: 99%

Emergency Decision Support Techniques for Nuclear Power Plants: Current State, Challenges, and Future Trends

Xiao,

Liang,

Tong

et al. 2024

Energies

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“…They invented Probabilistic Safety Assessment (PSA) that has proved to be an effective method for safety analysis and risk-based decisions [52]. Lu and Jiang provided an overview of PSA applications in three areas of digital Instrumentation and Control (IC) systems in nuclear power plants [53]. Radiation monitoring is one of the diagnosis methods for nuclear safeguards measurements which is used to protect against the theft of Special Nuclear Materials (SNM) by pedestrians departing from SNM access areas [54].…”

Section: Safeguards and Homeland Securitymentioning

confidence: 99%

Advanced Measuring (Instrumentation) Methods for Nuclear Installations: A Review

Wang

Lin

Yang

2012

Science and Technology of Nuclear Installations

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The nuclear technology has been widely used in the world. The research of measurement in nuclear installations involves many aspects, such as nuclear reactors, nuclear fuel cycle, safety and security, nuclear accident, after action, analysis, and environmental applications. In last decades, many advanced measuring devices and techniques have been widely applied in nuclear installations. This paper mainly introduces the development of the measuring (instrumentation) methods for nuclear installations and the applications of these instruments and methods.

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“…One of the challenges that has received much attention is the development of a consensus method for the probabilistic safety assessment (PSA) of digital I&C systems in NPPs. Lu and Jiang [2] provided an overview of PSA applications in three areas of digital I&C systems in NPPs. Kang et al [3] provided an overview of the risk quantification issues related to the digitalized safety systems in NPPs.…”

Section: Introductionmentioning

confidence: 99%

Important factors affecting fault detection coverage in probabilistic safety assessment of digital instrumentation and control systems

Kim

Lee

2014

Journal of Nuclear Science and Technology

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As digital instrumentation and control (I&C) systems are gradually introduced into nuclear power plants (NPPs), concerns about the I&C systems' reliability and safety are growing. Fault detection coverage is one of the most critical factors in the probabilistic safety assessment (PSA) of digital I&C systems. To correctly estimate the fault detection coverage, it is first necessary to identify important factors affecting it. From experimental results found in the literature and the authors' experience in fault injection experiments on digital systems, four system-related factors and four fault-related factors are identified as important factors affecting the fault detection coverage. A fault injection experiment is performed to demonstrate the dependency of fault detection coverage on some of the identified important factors. The implications of the experimental results on the estimation of fault detection coverage for the PSA of digital I&C systems are also explained. The set of four system-related factors and four fault-related factors is expected to provide a framework for systematically comparing and analyzing various fault injection experiments and the resultant estimations on fault detection coverage of digital I&C systems in NPPs.

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Probabilistic Safety Assessment for Instrumentation and Control Systems in Nuclear Power Plants: An Overview

Cited by 12 publications

References 16 publications

Emergency Decision Support Techniques for Nuclear Power Plants: Current State, Challenges, and Future Trends

Emergency Decision Support Techniques for Nuclear Power Plants: Current State, Challenges, and Future Trends

Advanced Measuring (Instrumentation) Methods for Nuclear Installations: A Review

Important factors affecting fault detection coverage in probabilistic safety assessment of digital instrumentation and control systems

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