All Stories

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