All Stories

  1. A framework for multi-target temperature profile generation using functional PCA and Gaussian mixture models for Fire PRA
  2. Towards area-dependent, scenario-based multi-hazard models: Part B – Case studies
  3. Foreword: Special Issue Featuring Papers from the 2024 Advanced Reactor Safety Topical Meeting (ARS 2024)
  4. Towards area-dependent, scenario-based multi-hazard models: Part A – Introduction to the OpenMHA methodology
  5. Efficient Algorithms for BDD-Based Uncertainty Quantification in Probabilistic Risk Assessment
  6. Cross-Entropy Adaptive Importance Sampling for Large Fault Trees with Structure-Informed Proposals and Scenario-Based Cut Set Extraction
  7. Impact of Large Power Transformer Bushing Seismic Vulnerability on the Electrical Grid
  8. The Development, Implementation, and Application of a Probabilistic Risk Assessment Framework to Evaluate Supply Chain Shortages
  9. Benchmarking study of ASYST code against CORA-18 BWR experiment with integrated uncertainty analysis
  10. Autoencoders for sparse sensory reconstruction of temperature gradients during critical power excursion accident conditions of nuclear reactors
  11. A Systematic Diagnostics and Enhancement Framework for Advancing Probabilistic Risk Assessment Tools
  12. Enhancement Assessment Framework for Probabilistic Risk Assessment Tools
  13. The Development, Implementation, and Application of a Probabilistic Risk Assessment Framework to Evaluate Supply Chain Shortages
  14. Integrated probabilistic risk assessment framework for transporting microreactors with a case study for road, rail, and maritime transportation modes
  15. Fail-Safe Material Limits for Chloride and Fluoride Molten Salt Experiments at the Advanced Test Reactor
  16. Advancing Multi-Hazard Risk and Safety Considerations for Aging Nuclear Facilities
  17. Autoencoders for Sparse Sensory Reconstruction of Temperature Gradients During Critical Power Excursion Accident Conditions of Nuclear Reactors
  18. Benchmarking Study of Asyst Code Against Cora-18 Bwr Experiment with Integrated Uncertainty Analysis
  19. Towards Area-Dependent, Scenario-Based Multi-Hazard Models: Part B – Case Studies
  20. Towards Area-Dependent, Scenario-Based Multi-Hazard Models: Part a – Introduction to the Openmha Methodology
  21. An Event Tree/Fault Tree Based Methodology for Integrated Multi-Hazard Risk Assessment
  22. Analysis of Radiological Release From Fueled Irradiation Experiments During Manual Handling
  23. Automated OpenPSA Model Generation from Reliability Diagrams Using Agentic Retrieval-Augmented Generation: A Case Study on MHTGR
  24. Bridging Deterministic and Probabilistic Safety Models for Advanced Nuclear Reactors Through Inverse Uncertainty Quantification
  25. Design and Implementation of a Distributed Queueing System for OpenPRA
  26. Determining Risk Significant Digital I&C Failure Modes in the Probabilistic Risk Assessment of a Nuclear Power Plant
  27. Enhancing ADS-IDAC with High-Performance Computing: Implementation Challenges and Preliminary Results
  28. Enhancing Expert Elicitation in Probabilistic Risk Assessment for Advanced Reactors: A Counterfactual and Causal Modeling Approach
  29. Evaluation of Recent Advances in Multi-Hazard Risk Assessment
  30. Facilitating PRA Model Accessibility: Model Converter Utility from SAPHIRE to OpenPSA
  31. Git Application for Configuration Control Programs of Advanced Nuclear Power Plants
  32. Implications of License Renewal of Aging NPPs: A Case Study on the Impact of External Hazards on an Aging Containment Building
  33. Incorporating Fault Injection Testing Results of Digital I&Cs into Probabilistic Risk Assessments of Nuclear Power Plants
  34. Integrated Simulation-Based Radiological Assessment of Depressurization Event Scenarios in High Temperature Gas Cooled Reactors
  35. Multi-Unit Modeling Challenges and Considerations for Xe-100 PRA Event Sequence Models
  36. Operational Experience and Development of a Reliability Model for the Advanced Test Reactor Demineralizer System
  37. Preliminary Assessment of Bleed and Feed During Total Loss of Feedwater (TLOFW) Accident in a 4-Loop PWR to Inform Dynamic PRA (DPRA) Efforts
  38. Probability Estimation Using Monte Carlo Simulation of Boolean Logic on Hardware-Accelerated Platforms
  39. Refining Failure Probability Estimation in Advanced Nuclear Reactors through Inverse Problem Computation
  40. Risk-Informed Emergency Planning Zone for Sodium Cooled Reactors: EBR-II Case Study
  41. Synthetical Model Generator for Probabilistic Risk Assessment Tools: Enhancing Testing, Verifying and Learning
  42. A missing data processing method for dam deformation monitoring data using spatiotemporal clustering and support vector machine model
  43. Mirror the mind of crew: Maritime risk analysis with explicit cognitive processes in a human digital twin
  44. Identifying and quantifying a complete set of full-power initiating events during early design stages of high-temperature gas-cooled reactors
  45. Aalo Atomics' High Level Licensing Strategy
  46. Addressing Uncertainties Across All Design Stages of Advanced Reactors Development
  47. Advancing SAPHIRE: Transitioning from Legacy to State-of-Art Excellence
  48. Data Updating Model Development with Bayesian Inference for Data Analysis for Probabilistic Risk Assessment Application
  49. Enhancing the SAPHIRE Solve Engine: Initial Progress and Efforts
  50. Evaluating PRA Tools for Accurate and Efficient Quantifications: A Follow-Up Benchmarking Study Including FTREX
  51. Implementing Multiple Control Paths in the Dual Error Propagation Graph for Stochastic Failure Analysis of Digital Instrumentation and Control Systems
  52. Introducing OpenPRA's Quantification Engine: Exploring Capabilities, Recognizing Limitations, and Charting the Path to Enhancement
  53. Laying the Foundations for the Development of a Probabilistic Model Checking Method to Quantify Common Cause Failure Parameters in Digital Instrumentation and Control
  54. Leveraging Inverse Uncertainty Quantification to Enhance the Resilience of Nuclear Power Plant Construction Duration Estimation
  55. On the Applicability of the General Transient Initiating Event Group for Advanced Reactors
  56. OpenMHA: Open-Source Code for Creating Multi-Hazards Logic and Area PRA Models Considering Aging of SSCs
  57. Primary Site Selection for Air Freight Transport of Department of Defense Microreactors
  58. Quantification of In-Containment Mechanistic Source Term for Advanced Light Water Reactor
  59. Quantifying Safety System Unavailability Margins via Inverse Estimation of Event Sequence Frequencies
  60. The State of Art of the Human Failure Events Dependency Analysis Methods
  61. Towards a Deep-Learning based Heuristic for Optimal Variable Ordering in Binary Decision Diagrams to Support Fault Tree Analysis
  62. Introducing OpenPRA: A Web-Based Framework for Collaborative Probabilistic Risk Assessment
  63. Leveraging Probabilistic Risk Assessment and Machine Learning for Safety and Cost Optimization in HAZMAT Transportation
  64. Probabilistic Risk Assessment Approach for the Transportation of Micro Reactors: Evaluating the Impact of Highway Accidents on the Surrounding Population
  65. Probabilistic Risk Assessment Study for Uncertainty Quantification of Spent Pebble-Bed Dry Cask Storage System Operation
  66. Integrating Commercial-Off-The-Shelf Components into Radiation-Hardened Drone Designs for Nuclear-Contaminated Search and Rescue Missions
  67. Motion Prediction of Tugboats Using Hidden Markov Model
  68. Dynamic Probabilistic Risk Assessment of Commercial-Off-The-Shelf Drones in Nuclear-Contaminated Search and Rescue Missions
  69. Investigating the applicability of human reliability analysis methods during early design stages of non-light-water nuclear power plants
  70. Erratum to “Pool inlet LOCA safety analysis in support of the emergency core spray system success criteria development of the PULSTAR research reactor” [Nucl. Eng. Design 403 (2023) 112163]
  71. A Limited-Scope Probabilistic Risk Assessment Study to Risk-Inform the Design of a Fuel Storage System for Spent Pebble-Filled Dry Casks
  72. A combined strategy for dynamic probabilistic risk assessment of fission battery designs using EMRALD and DEPM
  73. Pool inlet LOCA safety analysis in support of the emergency core spray system success criteria development of the PULSTAR research reactor
  74. Analyzing Hardware and Software Common Cause Failures in Digital Instrumentation and Control Systems Using Dual Error Propagation Method
  75. Characterization of Dynamic Behaviors in Licensee Event Report Data to Support PRA
  76. Creating Annotated Corpus and Named Entity Recognition Model for Nuclear Power Industry
  77. High-Performance Computing Implementation for ADS-IDAC
  78. Integrating Seismic Fragility of ASR-Affected Nuclear Containment Vessel in a Level-II SPRA in Support of Multi-Hazard Risk Assessment
  79. Introducing Multiple Control Paths in the Dual Error Propagation Graph for Stochastic Failure Analysis of Digital Instrumentation and Control Systems
  80. Method of Developing a SCRAM Parallel Engine for Efficient Quantification of Probabilistic Risk Assessment Models
  81. Methodology and Demonstration for Performance Analysis of a Probabilistic Risk Assessment Quantification Engine: SCRAM
  82. Model Exchange Methodology Between Probabilistic Risk Assessment Tools: SAPHIRE and CAFTA Case Study
  83. Preliminary Benchmarking of SAPHSOLVE, XFTA, and SCRAM Using Synthetically Generated Fault Trees with Common Cause Failures
  84. Preliminary Nuclear Containment Vessel Modeling for Multi-Hazard Probabilistic Risk Assessment Under Seismic Hazards and Concrete Degradation
  85. Quantifying the Likelihood of Nuclear Supply Chain Shortage Risk
  86. Time-Dependent Fragility Curves for SSCs: Incorporating Seismic Aftershocks in Multi-Hazard PRA
  87. Xe-100 PRA Event Sequence Modeling Framework
  88. Xe-100 PRA Initiating Events and Human Reliability Analysis Modeling Frameworks During the Early Design Stages
  89. Assessing the Potential for Implementation of Distributed Ledger Technology in the Nuclear Power Plant Lifecycle
  90. Automated Generation of Hybrid Probabilistic Risk Models From SysML V2 Models of Software-Defined Manufacturing Systems
  91. Benchmark Study of XFTA and SCRAM Fault Tree Solvers Using Synthetically Generated Fault Trees Models
  92. Preliminary Siting, Operations, and Transportation Considerations for Licensing Fission Batteries in the United States
  93. Implementing Probabilistic Design Methods in Plant Systems Design
  94. A framework to implement human reliability analysis during early design stages of advanced reactors
  95. A human reliability assessment model for the cognitive process of MASS shore-based operator applied, to dynamic probabilistic risk assessment platform
  96. Investigating the Applicability of Human Reliability Analysis Methods During Early Design Stages of Non-Light-Water Nuclear Power Plants
  97. Pool Inlet Loca Safety Analysis in Support of the Emergency Core Spray System Success Criteria Development of the Pulstar Research Reactor
  98. A Quantitative Approach to Assess the Likelihood of Supply Chain Shortages
  99. Demonstration of a Limited Scope Probabilistic Risk Assessment for Autonomous Warehouse Robots With OpenPRA
  100. Evaluating the Implementation of Distributed Ledger Technology for the Licensing and Regulation of Nuclear Power Plants
  101. On the Modeling of Wildfires-Induced Release and Atmospheric Dispersion in Radioactively Contaminated Regions
  102. On the Use of Probabilistic Risk Assessment for the Protection of Small Modular Reactors Against Terrorist Attacks
  103. Verification Study of the Nuclear PRA for the Mars 2020 Mission Following Accidental Orbital Re-Entry
  104. A Critical Look at the Need for Performing Multi-Hazard Probabilistic Risk Assessment for Nuclear Power Plants
  105. On the Use of the Accident Dynamic Simulator Method in Ship Collision Accident Analysis
  106. Method and software platform for electronic COTS parts reliability estimation in space applications
  107. A Hybrid Methodology for Model-Based Probabilistic Resilience Evaluation of Dynamic Systems
  108. On the Use of the Accident Dynamic Simulator Method in Ship Collision Accident Analysis
  109. A Comparative Assessment of Collision Risk of Manned and Unmanned Vessels
  110. On the Use of the Hybrid Causal Logic Methodology in Ship Collision Risk Assessment
  111. A Dynamic Pipeline Network Health Assessment Software Platform for Optimal Risk-Based Prioritization of Inspection, Structural Health Monitoring, and Proactive Management
  112. A Numerical and Experimental Study Supporting a Methodology for Live Monitoring, Leak Detection, and Automatic Response in Water Pipelines
  113. A Smart Pipeline Monitoring and Emergency Response System Using Web Services
  114. Model-Based Resilience Assessment Framework for Autonomous Systems
  115. Branching rules and quantification based on human behavior in the ADS-IDAC dynamic PRA platform
  116. HYPRA
  117. Optimization of Deep Borehole Systems for HLW Disposal
  118. Magnetic-field-induced nematic–nematic phase separation and droplet formation in colloidal goethite
  119. Onsager Revisited: Magnetic Field Induced Nematic−Nematic Phase Separation in Dispersions of Goethite Nanorods