SICA – a Software Complexity Analysis Method for the Failure Probability Estimation

Risk-informed Cyber Security Evaluation of Nuclear Facilities

MODIG – MODelling the Reliability of DIGital I&C in Modern Nuclear Power Plants

Risk Assessment of Cyber-attacks on Nuclear Power Plants

Probabilistic Assessment of Nuclear Piping Integrity by Using Recent Environmental Fatigue Equations

Floor Response Spectrum of a Base-isolated Nuclear Power Plant Considering Second Hardening of the Isolator System

Seismic Fragility of APR1400 Main Steam Piping System

Study on Floor Response Spectra by Parameter Uncertainty for Base Isolated Nuclear Power Plant Structures

A Process for Identifying Unsafe Act for HEP Quantification with Simulated Off-normal Training Records

Integrated HRA Analyzing Framework Using a Generic Task Database

Estimating HEPs and PSF Effects Using Full-scope Simulator Data: A Preliminary Study

Estimating HEPs from the Operational Experience of Domestic Nuclear Power Plants – a Framework and Case Studies

Study on Quantification Methodology of Accident Sequences for Tsunami Induced by Seismic Events

Event Sequence Assessment of Tornado and Strong Wind in Sodium Cooled Fast Reactor Based on Continuous Markov Chain Monte Carlo Method with Plant Dynamics Analysis

Data Collection in Fire PSA

A Review of the Progress with Statistical Models of Passive Component Reliability

Development and Application of Source Term Analysis Framework on OPR-1000 NPP for Radiological Emergency Preparedness

State-of-the-art Reactor Consequence Analyses Project: Uncertainty Analysis of a Potential Unmitigated Short-term Station Blackout at the Surry Nuclear Power Station

Flushing Water Contamination in Different Concrete Models for PSA Level 3 Severe Accident Scenario

Finnish Experiments on Level 3 PRA

Review of International Source Term Release Histories for the Establishment of Radiological Emergency Preparedness Framework of Nuclear Power Plant

Concept of Defence-in-depth against External Events in Japan

Development of Evaluation Method for Probabilistic Seismic and Tsunami Hazards Considering Events Superimposition

Internal Flooding PRA for Kashiwazaki-Kariwa Nuclear Power Plants

Application of Dynamic Probabilistic Risk Assessment to a Seismically-induced Internal Flood Event

Holistic Approach to Multi-unit Site Risk Assessment: Status and Issues

A Pilot Study on Developing a Site Risk Model

Linking of Event Trees via Analysis Results

MCS BDD – Description and Verification of the Method Implemented in RiskSpectrum

Exhausted Test Case for Software Reliability of Nuclear Digital Systems

Aleatory Uncertainty Appeared in Strong Nonlinear Behavior such as Slope Collapse

Enhanced Monte Carlo Simulation-based Spatial Reliability Analysis of RC Plate Subject to Chloride-induced Corrosion

The Case Study on Breakout Shear Failure in Concrete related to Anchor Edge Distance in Safety-Related Equipment Seismic Fragility Analysis

Improved Guidance for the Application of Recovery Factors for Human Reliability Analysis (HRA) Method Caused Based Decision Tree (CBDT)

Evaluation of Existing Applications and Guidance on Methods for HRA – EXAM-HRA

Upgrade of the Spent Fuel Pool PSA for NPP Paks Motivated by the Change in Emergency Operating Procedures

Simulated Human Error Probability and Its Application to Dynamic Human Failure Events

Use of Minimum Bounds for Joint Human Error Probabilities in PRA

Accident Sequence Precursor Analysis in Czech Republic

Use of Risk-informed Technique to Evaluate the Balance of Technical Specification

Risk Informed Unavailability Management (introducing Balance Time Instead of AOT)

Spatio-Temporal Socio-Technical Risk Analysis Methodology for Emergency Response

Numerical Simulation of PHEBUS FPT-3 Experiment by Using COMPASS Code

Development of a Fission Product Transport Module Predicting Aerosol Behavior in the RCS of a Nuclear Power Plant during Severe Accidents

Extended Loss of AC Power (ELAP) Analysis of Kuosheng BWR/6 Using MELCOR2.1/SNAP

MAAP5 Application to in-vessel Retention Analysis for Pressurized Light Water Reactors

Water Injection Influence for Accident Progression in Fukushima Dai-ichi Unit1

A Study of Screening Method for the Risk Significant Combinations among the External Hazards

IRSN Methodology for the Selection of External Hazards Candidate to Probabilistic Analysis

The Systematic Evaluation of Combining Extreme Hazards for Lungmen Nuclear Power Plant

Non-seismic External Event Level 1 PSA for the WWER440 Type Reactors

Extreme Event Analysis – A Benchmarking Study at Armenian Nuclear Power Plant to Examine Plant Robustness against the Impact of Extreme Events

Comparison of Approximate Response Functions to Assess the Extent of Radiological Consequences after a Nuclear Accident

A Pilot Choice Experiment among French Nuclear Specialists to Measure the Intangible Value of Territories

Important Considerations in Selecting a Simulation End-time in Level 2 PSA Deterministic Analyses

The Development of Nordic Guidance in Level 3 PSA

The OECD/NEA CODAP Project & Its Contribution to Plant Aging Management & Probabilistic Safety Assessment

A Field Data Based RAM Analysis and Classification of Intensive Management Items for the Korean Utility Helicopters

Probabilistic Seismic Risk Assessment of Lifeline Networks Using Cross-entropy-based Adaptive Importance Sampling

Seismic Fragility Analysis of an Asymmetrical Reinforced Concrete Building Considering Soil-structure Interaction Effect

Systems Engineering Approach to Dynamic Probabilistic Safety Analysis Using GPGPU Parallel Computing

Curtiss-Wright/Scientech Seismic HRA Insights and Lessons Learned from the Application of EPRI Report TR-1025294

Modeling Main Control Room Abandonment Due to Fire-induced Loss of Control in Fire Probabilistic Risk Assessment

Summary of Joint EPRI/NRC-RES Main Control Room Abandonment Research Project

Identification of Important Human Actions via a Combination of Probabilistic and Deterministic Analyses

Alternative Human-machine Interfaces for Coping with Team Errors in the Digitalized Control Room of Nuclear Power Plants

Development of Accident Scenarios for Shutdown Probabilistic Safety Assessment

A Semi-supervised Self Organizing Map for Post-processing the Scenarios of an Integrated Deterministic and Probabilistic Safety Analysis

Directions Towards Supporting Synergies between Design and Probabilistic Safety Assessment Activities: Illustration on a Fire Detection System Embedded in a Helicopter

PSA Application in the Diverse Actuation System Design

Safety Management of a Nuclear-based Hydrogen Generation System

Influence of T-H Model’s Uncertainty on Natural Circulation

Output Updating in Severe Accident Uncertainty Assessment; A Bayesian Framework

A Study of Developing a Plant Did Risk Monitor for Resilient Severe Accident Management

Methodology for Crediting Severe Accident Management Guidance in Probabilistic Safety Assessment

Passive High-pressure Safety Injection of Hybrid-safety Injection Tank

Frequency of Frazil Ice and Algae Threats to Ultimate Heat Sink for Hanhikivi-1 NPP

A Computational Scheme for Tornado Missile Strike Probability Using Stochastic Correlation between Local Wind Speed and Flight Distance

An Analysis of the Hazards to a Nuclear Reactor from Meteors

Analysing and Decreasing External Event Risks of Loviisa NPP