Recent research towards integrated deterministic-probabilistic safety assessment in Korea

Heo, Gyunyoung; Baek, Sejin; Kwon, Daewoong; Kim, Hyeonmin; Park, Jinkyun

doi:10.1016/j.net.2021.05.015

Cited by 20 publications

(4 citation statements)

References 54 publications

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“…These approaches are somewhat complementary to each other. Some researchers integrate PSA with DSA to conduct risk analysis [14,[102][103][104][105]. This hybrid approach synergizes the strengths of both methodologies, enhancing the comprehensiveness and accuracy of risk assessments in NPP operations.…”

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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“…Owing to the advancements in computer performance in recent years, various tools have been developed and applied to safety issues in nuclear power plants since then. [12][13][14][15][16][17][18] The Japan Atomic Energy Agency (JAEA) has developed a dynamic PRA methodology and tool called Risk Assessment with Plant Interactive Dynamics (RAPID) [19][20][21][22][23] to technically support NRA. RAPID has been used to evaluate nuclear-power-plant safety issues, including external event-induced risk.…”

Section: Introductionmentioning

confidence: 99%

“…Owing to the advancements in computer performance in recent years, various tools have been developed and applied to safety issues in nuclear power plants since then. 12–18…”

Section: Introductionmentioning

confidence: 99%

Quantification of risk dilution induced by correlation parameters in dynamic probabilistic risk assessment of nuclear power plants

Kubo

Tanaka

Ishikawa

2023

Proceedings of the Institution of Mechanical Engineers, Part O:

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Nuclear power plants are critical infrastructures that produce electricity. However, accidents in nuclear power plants can cause considerable consequences such as the release of radioactive materials. Therefore, appropriately managing their risk is necessary. Various nuclear regulatory agencies employ probabilistic risk assessment (PRA) to effectively evaluate risks in nuclear power plants. Dynamic PRA has gained popularity because it allows for more realistic assessment by reducing the assumptions and engineering judgments related to time-dependent failure probability and/or human-action reliability in the conventional PRA methodology. However, removing all assumptions and engineering judgments is difficult; thus, the risk analyst, for example, the regulator, must understand their effects on the assessment results. This study focuses on “risk dilution,” which emerges from the assumptions about uncertainty. Dynamic PRA of a station blackout sequence in a boiling-water reactor was performed using the dynamic PRA tool, namely, Risk Assessment with Plant Interactive Dynamics (RAPID) and the severe-accident code Thermal–Hydraulic Analysis of Loss of Coolant, Emergency Core Cooling, and Severe Core Damage version 2 (THALES2), which altered the correlation parameters among the uncertainties of the events that occurred in sequence. The results demonstrated that the conditional core-damage probability and mean value of the core-damage time varied from 0.27 to 0.47 and from 7.1 to 8.7 h, respectively. When the dynamic PRA results are used for risk-informed decision making, the decision maker should adequately consider the effect of risk dilution.

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“…MCDET (Monte Carlo dynamic event tree) enables the proper use of the Monte Carlo method and DDET [15,16]. Tools such as ADAPT (analysis of dynamic accident progression trees) [17,18], SCAIS (simulation code system for integrated safety assessment) [19,20], PyCATSOO (Pythonic object-oriented hybrid stochastic automata) [21,22], DICE (dynamic integrated consequence evaluation) [23,24], MOSAIQUE (module for sampling input and quantifying estimator) [25,26] have also been developed.…”

Section: Introductionmentioning

confidence: 99%

Accident Sequence Precursor Analysis of an Incident in a Japanese Nuclear Power Plant Based on Dynamic Probabilistic Risk Assessment

Kubo

2023

Science and Technology of Nuclear Installations

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Probabilistic risk assessment (PRA) is an effective methodology that could be used to improve the safety of nuclear power plants in a reasonable manner. Dynamic PRA, as an advanced PRA, allows for more realistic and detailed analyses by handling time-dependent information. However, the applications of this method to practical problems are limited because it remains in the research and development stage. This study aimed to investigate the possibility of utilizing dynamic PRA in risk-informeddecision-making. Specifically, the author performed an accident sequence precursor (ASP) analysis on the failure of emergency diesel generators that occurred at Unit 1 of the Tomari Nuclear Power Plant in Japan using dynamic PRA. The results were evaluated by comparison with the results of simplified classical PRA. The findings indicated that dynamic PRA may estimate lower risks compared with those obtained from classical PRA by reasonable modeling of alternating current power recovery. The author also showed that dynamic PRA can provide detailed information that cannot be obtained with classical PRA, such as uncertainty distribution of core damage timing and importance measure considering the system failure timing.

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Recent research towards integrated deterministic-probabilistic safety assessment in Korea

Cited by 20 publications

References 54 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

Quantification of risk dilution induced by correlation parameters in dynamic probabilistic risk assessment of nuclear power plants

Accident Sequence Precursor Analysis of an Incident in a Japanese Nuclear Power Plant Based on Dynamic Probabilistic Risk Assessment

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