Jiandong He’s research while affiliated with Shanghai Nuclear Engineering Research and Design Institute and other places

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Publications (5)


Fire Human Reliability Analysis for C-2 Nuclear Power Plant
  • Chapter

May 2023

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6 Reads

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1 Citation

Yongping Qiu

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Yucheng Zhuo

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Guixue Zhu

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[...]

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As one of the essential tasks of fire Probabilistic Safety Assessment (PSA), fire Human Reliability Analysis (HRA) has important impact on analysis results and quality of a fire PSA. The scope of a fire HRA mainly includes pre-initiator HRA and post-initiator HRA. In this paper, the screening methodology for the post-initiator HRA of CHASHMA Nuclear Power Plant Unit 2 (C-2) is first introduced briefly with the screening criteria, and the performance shaping factors (PSFs) that should be considered in the fire HRA are studied. Next the post-initiator human failure events (HFEs) for C-2 nuclear power plant are identified and the preliminary quantitative analysis is presented with the screening method. Finally, the detailed quantification of HFEs with the Standardized Plant Analysis Risk Human Reliability Analysis (SPAR-H) method is described briefly and the analysis results are all obtained. The dependency analysis and uncertainty analysis in C-2 fire HRA are also briefly discussed in this paper.KeywordsFire human reliability analysisPost-initiatorHuman failure eventsPerformance shaping factorsDependency analysis


Development and Application of CAP1400 Probabilistic Safety Assessment

July 2017

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18 Reads

A full scope Probabilistic Safety Assessment (PSA) is developed for CAP1400 and some design modification was performed based on the CAP1400 PSA insights. In this paper, a brief introduction of CAP1400 PSA is presented, including analysis method, procedure, results and insights obtained and design improvements. The CAP1400 PSA includes internal events level 1 PSA, low power and shutdown PSA, level 2 PSA, level 3 PSA, internal fire PSA, internal flooding PSA, seismic margin analysis and seismic PSA, etc. The CAP1400 PSA is developed based on PSA methods acknowledged internationally and in compliance with the requirement of PSA related standards, such as ASME PSA standards and Chinese PSA standards. The design improvements derived from PSA results are also introduced in this paper, including design change of passive core cooling system (PXS), diverse design of instrument and control system, design change of in-vessel retention (IVR) of molten core debris, installation of very early warning fire detection system and design change of flooding protection of PXS valves.


Methodology and Application of Human Reliability Analysis in CAP1400 Nuclear Power Plant

July 2017

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25 Reads

It is well recognized that humans play an important role in the safety operation of nuclear power plants (NPPs). Usually three types of human interactions (HIs) are defined in the human reliability analysis (HRA) of probabilistic safety assessment (PSA) for NPPs, i.e., pre-initiating event HIs, initiating event-related HIs, and post-initiating event HIs. In this paper, a brief introduction of the HRA methodology for CAP1400 nuclear power plant is first presented, including internal events and external events (mainly internal fire and flooding) HRA. Next, the CAP1400 human failure event quantification content is given with a typical example, and some insights and proposals based on CAP1400 PSA/HRA results are discussed. Finally, the application of HRA in human factor engineering design of CAP1400 is described. The human actions (HAs) most important to safety are identified via a combination of probabilistic and deterministic analyses, and then addressed when conducting the human factor engineering program. The CAP1400 HRA is one of the most important PSA elements and provides fundamental support for CAP1400 PSA and the relevant applications.


Identifying Key Performance Shaping Factors in Digital Main Control Rooms of Nuclear Power Plants: A Risk-based Approach

June 2017

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142 Reads

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28 Citations

Reliability Engineering & System Safety

Various human reliability analysis (HRA) methods use performance shaping factors (PSFs) to model operator performance. The tendency in HRA is to increase the number of PSFs. However, using many PSFs may negatively affect the quality of HRA outcomes. An elite-set PSF model with key PSFs is lacking. We therefore suggest a risk-based approach for identifying the key PSFs by ranking their risks to operator performance. In this approach, we elicit nuclear power plant (NPP) operators’ perceptions of the frequency and impact of PSF indicators in main control rooms (MCRs), quantify the perceived risk scores of PSFs by multiplying their perceived frequency and impact, and classify PSF risk levels according to the suggested PSF risk matrix. Licensed operators (N = 33) from a digital NPP MCR participated in our survey. The top-ranked PSFs in terms of perceived risk score and the PSFs at the High Risk level were identified as the key PSFs from the surveyed NPP MCR. A comparison with other studies indicates that the importance of these key PSFs has been previously recognized, implying that the risk-based approach can yield meaningful results for ranking and identifying the key PSFs.


Conceptualizing Performance Shaping Factors in Main Control Rooms of Nuclear Power Plants: A Preliminary Study

July 2016

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62 Reads

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15 Citations

Lecture Notes in Computer Science

Human errors are widely-accepted to be a major contributor to incidents and accidents in complex, safety-critical systems. Human reliability is influenced by individual, organizational, and environmental factors, which are called as performance shaping factors (PSFs). Identifying and managing PSFs are important for quantifying human error probability in human reliability analysis (HRA) and preventing human errors in main control rooms (MCRs) of nuclear power plants (NPPs). This study proposes a conceptualization framework for PSFs to identify and organize PSFs in MCRs of NPPs. It describes PSFs at three levels, components, factors (i.e., dimensions), and indicators. The expected result is the full-set PSF model for MCRs of NPPs. The future study is to weight and rank the PSFs from this full-set PSF model and to identify the elite-set PSF model with key PSFs to inform the HRA quantitative analysis.

Citations (2)


... For example, studies on human reliability in the field of NPPs identified and classified the Performance Shaping Factors (PSFs) models by asking NPP workers about their perceived impact of a given factor on the daily work. The results suggested that personalrelated factors, including one's physical or mental state, cognitive bias, and responsibility, have a high-risk effect on work in NPPs (Ghalenoei et al., 2022;Liu et al., 2017;Kim & Seong, 2019;Yin et al., 2021). The unsafe behaviors of commissioning workers may be caused by their poor personal states (Liu et al., 2017). ...

Reference:

Effects of personal states and personality traits on work performance of commissioning workers in nuclear power plants
Identifying Key Performance Shaping Factors in Digital Main Control Rooms of Nuclear Power Plants: A Risk-based Approach
  • Citing Article
  • June 2017

Reliability Engineering & System Safety

... They have also constructed a specific PSF overall multiplier quantitative framework to propose new PSF multipliers [27], which ultimately enables quantifying the degree of influence among the PSFs. Some studies have weighted and ranked the key PSFs by introducing a conceptual framework and a risk matrix for identifying and managing key PSFs [28,29]. ...

Conceptualizing Performance Shaping Factors in Main Control Rooms of Nuclear Power Plants: A Preliminary Study
  • Citing Conference Paper
  • July 2016

Lecture Notes in Computer Science