tailieunhanh - Human and organizational factors for multi-unit probabilistic safety assessment: Identification and characterization for the Korean case

This study identifies and categorizes the human and organizational factors relevant to a multi-unit incident scenario of NPPs based on a review of relevant literature. These factors are then analyzed to ascertain all possible unit-tounit interactions that need to be considered in the multi-unit HRA and the pattern of interactions. | Human and organizational factors for multi-unit probabilistic safety assessment: Identification and characterization for the Korean case Nuclear Engineering and Technology 51 (2019) 104e115 Contents lists available at ScienceDirect Nuclear Engineering and Technology journal homepage: Original Article Human and organizational factors for multi-unit probabilistic safety assessment: Identification and characterization for the Korean case Awwal Mohammed Arigi, Gangmin Kim, Jooyoung Park, Jonghyun Kim* Department of Nuclear Engineering, Chosun University, 309 Pilmun-daero, Dong-gu, Gwangju, 501-709, Republic of Korea a r t i c l e i n f o a b s t r a c t Article history: Since the Fukushima Daiichi accident, there has been an emphasis on the risk resulting from multi-unit Received 21 March 2018 accidents. Human reliability analysis (HRA) is one of the important issues in multi-unit probabilistic Received in revised form safety assessment (MUPSA). Hence, there is a need to properly identify all the human and organizational 20 July 2018 factors relevant to a multi-unit incident scenario in a nuclear power plant (NPP). This study identifies and Accepted 29 August 2018 Available online 7 September 2018 categorizes the human and organizational factors relevant to a multi-unit incident scenario of NPPs based on a review of relevant literature. These factors are then analyzed to ascertain all possible unit-to- unit interactions that need to be considered in the multi-unit HRA and the pattern of interactions. The Keywords: Multi-unit PSA human and organizational factors are classified into five categories: organization, work device, task, Unit-to-unit interaction performance shaping factors, and environmental factors. The identification and classification of these Multi-unit HRA factors will significantly contribute to the development of adequate strategies and guidelines for man- Human and .

• Năng lượng
• Nuclear engineering and technology
• Human for multi unit probabilistic safety assessment
• Organizational factors for multi unit probabilistic safety assessment
• Multi unit probabilistic safety assessment
• Identification and characterization for the Korean case
• Integral nuclear data validation
• Experimental spent nuclear fuel compositions
• Economic Co operation and Development
• Nuclear Energy Agency
• Nuclear Criticality Safety
• Expanded spent fuel isotopic compositions
• Nuclear reactor vessel water level prediction during severe accidents
• Deep neural networks
• Nuclear power plants
• Maintain nuclear reactor integrity
• Special issue on the International Symposium
• Future Instrumentation and Control for Nuclear Power Plants
• The Nuclear Engineering and Technolog
• Parameter identifiability of Boolean networks
• Application to fault diagnosis of nuclear plants
• Fault diagnosis of nuclear plants
• Nuclear Heating Reactor
• Sensor selection strategy
• Radioactive effluents released from Korean nuclear power plants
• The resulting radiation doses to members of the public
• Korean nuclear power plants
• Nuclear power plant
• The recycling of nuclear graphite after micro oxidation
• Nuclear graphite after micro oxidation
• Whether ground micro oxidation graphite
• The oxidized graphite particles
• The recycling of nuclear graphite
• Statistical model for forecasting uranium prices
• Estimate the nuclear fuel cycle cost
• Nuclear Fuel Cycle Cost
• Nuclear fuel cycle cost calculation
• The statistical autoregressive integrated moving average
• Distinct properties of tungsten austenitic stainless alloy
• Potential nuclear engineering material
• Interchanging the molybdenum in standard SS316 by tungsten
• Gamma and neutron shielding Interchanging the molybdenum
• Nuclear engineering and design
• Brayton cycle
• Supercritical carbon dioxide
• Nuclear engineering
• Safety analysis
• Control strategy
• Seismic fragility evaluation
• The base isolated nuclear power plant piping system
• The failure criterion based on stress strain
• Nuclear power plant piping system
• Seismic fragility analysis
• BNL NRC benchmark model
• Feasibility study on photo production
• 99mTc with the nuclear resonance fluorescence
• The nuclear resonance fluorescence
• High intensity laser Compton scattering
• Improved PCA method
• Sensor fault detection and isolation in a nuclear power plant
• Sensor fault detection and isolation
• Influences of heating processes on properties
• Microstructure of porous CeO2 beads
• Surrogate for nuclear fuels fabricated
• Microfluidic sol gel process
• The ceramic nuclear fuel particles
• Sensitivity analysis of thermal hydraulic parameters
• The corrosion intensity in nuclear power plant steam generators
• Nuclear power plant steam generators
• The failure of steam generators
• The heat exchangers
• Architectural model driven dependability analysis
• Computer based safety system in nuclear power plant
• Safety system in nuclear power plant
• Embedded Real Time Safety Systems
• Mitigation of high energy arcing faults
• Nuclear power plant medium voltage switchgear
• High energy arcing fault
• Ultra high performance fiber reinforced concrete nuclear waste container
• High level waste
• Ultra high performance fiber reinforced concrete material
• The dry storage container
• Canadian Nuclear facilities
• Real time estimation of break sizes during LOCA
• Nuclear power plants using NARX neural network
• Nonlinear autoregressive with exogenous inputs
• Loss of coolant accidents
• Nordic research and development cooperation
• Strengthen nuclear reactor safety after the Fukushima accident
• The Fukushima accident
• Nordic Nuclear Safety Research
• Seismic response characteristics
• Isolated AP1000 nuclear shield building subjected
• Beyond design basis earthquake shaking
• Beyond Design Basis Earthquake
• Nuclear Shield Building
• Uncertainty analysis of containment dose rate
• Containment dose rate for core damage assessment
• Containment Radiation Monitor
• Core Damage Assessment
• An evaluation method for nuclear fuel debrisefiltering performance
• Nuclear fuel debrisefiltering performance
• Comprehensive Debris Filtering Efficiency
• Debris Filtering Performance
• Debris Induced Failure
• Development of earthquake instrumentation for shutdown
• Restart criteria of the nuclear power plant
• Multivariable decision making process
• The nuclear power plant
• Development of an information reference system
• Reconstruction models of nuclear power plants
• Work site reconstruction models
• Six nuclear power plant workers
• Nondestructive inspection of spent nuclear fuel storage canisters
• Shear horizontal guided waves
• Spent nuclear fuel storage canisters
• The cask protecting the canister
• Geometric constrains inside