All Stories

  1. Benchmarking study of ASYST code against CORA-18 BWR experiment with integrated uncertainty analysis

    Article • Nuclear Engineering and Design, October 2025, Elsevier

    Mihai Diaconeasa

  2. Autoencoders for sparse sensory reconstruction of temperature gradients during critical power excursion accident conditions of nuclear reactors

    Article • Nuclear Engineering and Design, September 2025, Elsevier

    Mihai Diaconeasa

  3. Integrated probabilistic risk assessment framework for transporting microreactors with a case study for road, rail, and maritime transportation modes

    Article • npj Clean Energy, August 2025, Springer Science + Business Media

    Mihai Diaconeasa

  4. Fail-Safe Material Limits for Chloride and Fluoride Molten Salt Experiments at the Advanced Test Reactor

    Article • March 2025, Springer Science + Business Media

    Mihai Diaconeasa

  5. Autoencoders for Sparse Sensory Reconstruction of Temperature Gradients During Critical Power Excursion Accident Conditions of Nuclear Reactors

    Article • January 2025, Elsevier

    Mihai Diaconeasa

  6. Benchmarking Study of Asyst Code Against Cora-18 Bwr Experiment with Integrated Uncertainty Analysis

    Article • January 2025, Elsevier

    Mihai Diaconeasa

  7. Towards Area-Dependent, Scenario-Based Multi-Hazard Models: Part B – Case Studies

    Article • January 2025, Elsevier

    Mihai Diaconeasa

  8. Towards Area-Dependent, Scenario-Based Multi-Hazard Models: Part a – Introduction to the Openmha Methodology

    Article • January 2025, Elsevier

    Mihai Diaconeasa

  9. An Event Tree/Fault Tree Based Methodology for Integrated Multi-Hazard Risk Assessment

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  10. Analysis of Radiological Release From Fueled Irradiation Experiments During Manual Handling

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  11. Automated OpenPSA Model Generation from Reliability Diagrams Using Agentic Retrieval-Augmented Generation: A Case Study on MHTGR

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  12. Bridging Deterministic and Probabilistic Safety Models for Advanced Nuclear Reactors Through Inverse Uncertainty Quantification

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  13. Design and Implementation of a Distributed Queueing System for OpenPRA

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  14. Determining Risk Significant Digital I&C Failure Modes in the Probabilistic Risk Assessment of a Nuclear Power Plant

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  15. Enhancing ADS-IDAC with High-Performance Computing: Implementation Challenges and Preliminary Results

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  16. Enhancing Expert Elicitation in Probabilistic Risk Assessment for Advanced Reactors: A Counterfactual and Causal Modeling Approach

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  17. Evaluation of Recent Advances in Multi-Hazard Risk Assessment

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  18. Facilitating PRA Model Accessibility: Model Converter Utility from SAPHIRE to OpenPSA

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  19. Git Application for Configuration Control Programs of Advanced Nuclear Power Plants

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  20. Implications of License Renewal of Aging NPPs: A Case Study on the Impact of External Hazards on an Aging Containment Building

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  21. Incorporating Fault Injection Testing Results of Digital I&Cs into Probabilistic Risk Assessments of Nuclear Power Plants

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  22. Integrated Simulation-Based Radiological Assessment of Depressurization Event Scenarios in High Temperature Gas Cooled Reactors

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  23. Multi-Unit Modeling Challenges and Considerations for Xe-100 PRA Event Sequence Models

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  24. Operational Experience and Development of a Reliability Model for the Advanced Test Reactor Demineralizer System

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  25. Preliminary Assessment of Bleed and Feed During Total Loss of Feedwater (TLOFW) Accident in a 4-Loop PWR to Inform Dynamic PRA (DPRA) Efforts

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  26. Probability Estimation Using Monte Carlo Simulation of Boolean Logic on Hardware-Accelerated Platforms

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  27. Refining Failure Probability Estimation in Advanced Nuclear Reactors through Inverse Problem Computation

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  28. Risk-Informed Emergency Planning Zone for Sodium Cooled Reactors: EBR-II Case Study

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  29. Synthetical Model Generator for Probabilistic Risk Assessment Tools: Enhancing Testing, Verifying and Learning

    Article • January 2025, American Nuclear Society (ANS)

    Mihai Diaconeasa

  30. A missing data processing method for dam deformation monitoring data using spatiotemporal clustering and support vector machine model

    Article • Water Science and Engineering, December 2024, Tsinghua University Press

    Mihai Diaconeasa

  31. Mirror the mind of crew: Maritime risk analysis with explicit cognitive processes in a human digital twin

    Article • Advanced Engineering Informatics, October 2024, Elsevier

    Mihai Diaconeasa

  32. Identifying and quantifying a complete set of full-power initiating events during early design stages of high-temperature gas-cooled reactors

    Article • Reliability Engineering & System Safety, February 2024, Elsevier

    Mihai Diaconeasa

  33. Aalo Atomics' High Level Licensing Strategy

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  34. Addressing Uncertainties Across All Design Stages of Advanced Reactors Development

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  35. Advancing SAPHIRE: Transitioning from Legacy to State-of-Art Excellence

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  36. Data Updating Model Development with Bayesian Inference for Data Analysis for Probabilistic Risk Assessment Application

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  37. Enhancing the SAPHIRE Solve Engine: Initial Progress and Efforts

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  38. Evaluating PRA Tools for Accurate and Efficient Quantifications: A Follow-Up Benchmarking Study Including FTREX

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  39. Implementing Multiple Control Paths in the Dual Error Propagation Graph for Stochastic Failure Analysis of Digital Instrumentation and Control Systems

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  40. Introducing OpenPRA's Quantification Engine: Exploring Capabilities, Recognizing Limitations, and Charting the Path to Enhancement

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  41. Laying the Foundations for the Development of a Probabilistic Model Checking Method to Quantify Common Cause Failure Parameters in Digital Instrumentation and Control

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  42. Leveraging Inverse Uncertainty Quantification to Enhance the Resilience of Nuclear Power Plant Construction Duration Estimation

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  43. On the Applicability of the General Transient Initiating Event Group for Advanced Reactors

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  44. OpenMHA: Open-Source Code for Creating Multi-Hazards Logic and Area PRA Models Considering Aging of SSCs

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  45. Primary Site Selection for Air Freight Transport of Department of Defense Microreactors

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  46. Quantification of In-Containment Mechanistic Source Term for Advanced Light Water Reactor

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  47. Quantifying Safety System Unavailability Margins via Inverse Estimation of Event Sequence Frequencies

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  48. The State of Art of the Human Failure Events Dependency Analysis Methods

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  49. Towards a Deep-Learning based Heuristic for Optimal Variable Ordering in Binary Decision Diagrams to Support Fault Tree Analysis

    Article • January 2024, American Nuclear Society (ANS)

    Mihai Diaconeasa

  50. Introducing OpenPRA: A Web-Based Framework for Collaborative Probabilistic Risk Assessment

    Article • October 2023, ASME International

    Mihai Diaconeasa

  51. Leveraging Probabilistic Risk Assessment and Machine Learning for Safety and Cost Optimization in HAZMAT Transportation

    Article • October 2023, ASME International

    Mihai Diaconeasa

  52. Probabilistic Risk Assessment Approach for the Transportation of Micro Reactors: Evaluating the Impact of Highway Accidents on the Surrounding Population

    Article • October 2023, ASME International

    Mihai Diaconeasa

  53. Probabilistic Risk Assessment Study for Uncertainty Quantification of Spent Pebble-Bed Dry Cask Storage System Operation

    Article • October 2023, ASME International

    Mihai Diaconeasa

  54. Integrating Commercial-Off-The-Shelf Components into Radiation-Hardened Drone Designs for Nuclear-Contaminated Search and Rescue Missions

    Article • Drones, August 2023, MDPI AG

    Mihai Diaconeasa

  55. Motion Prediction of Tugboats Using Hidden Markov Model

    Article • August 2023, Institute of Electrical & Electronics Engineers (IEEE)

    Mihai Diaconeasa

  56. Dynamic Probabilistic Risk Assessment of Commercial-Off-The-Shelf Drones in Nuclear-Contaminated Search and Rescue Missions

    Article • July 2023, MDPI AG

    Mihai Diaconeasa

  57. Investigating the applicability of human reliability analysis methods during early design stages of non-light-water nuclear power plants

    Article • Progress in Nuclear Energy, July 2023, Elsevier

    Mihai Diaconeasa

  58. 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]

    Article • Nuclear Engineering and Design, July 2023, Elsevier

    Mihai Diaconeasa

  59. A Limited-Scope Probabilistic Risk Assessment Study to Risk-Inform the Design of a Fuel Storage System for Spent Pebble-Filled Dry Casks

    Article • Eng—Advances in Engineering, June 2023, MDPI AG

    Mihai Diaconeasa

  60. A combined strategy for dynamic probabilistic risk assessment of fission battery designs using EMRALD and DEPM

    Article • Progress in Nuclear Energy, June 2023, Elsevier

    Mihai Diaconeasa

  61. Pool inlet LOCA safety analysis in support of the emergency core spray system success criteria development of the PULSTAR research reactor

    Article • Nuclear Engineering and Design, March 2023, Elsevier

    Mihai Diaconeasa

  62. Analyzing Hardware and Software Common Cause Failures in Digital Instrumentation and Control Systems Using Dual Error Propagation Method

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  63. Characterization of Dynamic Behaviors in Licensee Event Report Data to Support PRA

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  64. Creating Annotated Corpus and Named Entity Recognition Model for Nuclear Power Industry

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  65. High-Performance Computing Implementation for ADS-IDAC

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  66. Integrating Seismic Fragility of ASR-Affected Nuclear Containment Vessel in a Level-II SPRA in Support of Multi-Hazard Risk Assessment

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  67. Introducing Multiple Control Paths in the Dual Error Propagation Graph for Stochastic Failure Analysis of Digital Instrumentation and Control Systems

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  68. Method of Developing a SCRAM Parallel Engine for Efficient Quantification of Probabilistic Risk Assessment Models

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  69. Methodology and Demonstration for Performance Analysis of a Probabilistic Risk Assessment Quantification Engine: SCRAM

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  70. Model Exchange Methodology Between Probabilistic Risk Assessment Tools: SAPHIRE and CAFTA Case Study

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  71. Preliminary Benchmarking of SAPHSOLVE, XFTA, and SCRAM Using Synthetically Generated Fault Trees with Common Cause Failures

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  72. Preliminary Nuclear Containment Vessel Modeling for Multi-Hazard Probabilistic Risk Assessment Under Seismic Hazards and Concrete Degradation

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  73. Quantifying the Likelihood of Nuclear Supply Chain Shortage Risk

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  74. Time-Dependent Fragility Curves for SSCs: Incorporating Seismic Aftershocks in Multi-Hazard PRA

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  75. Xe-100 PRA Event Sequence Modeling Framework

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  76. Xe-100 PRA Initiating Events and Human Reliability Analysis Modeling Frameworks During the Early Design Stages

    Article • January 2023, American Nuclear Society (ANS)

    Mihai Diaconeasa

  77. Assessing the Potential for Implementation of Distributed Ledger Technology in the Nuclear Power Plant Lifecycle

    Article • October 2022, ASME International

    Mihai Diaconeasa

  78. Automated Generation of Hybrid Probabilistic Risk Models From SysML V2 Models of Software-Defined Manufacturing Systems

    Article • October 2022, ASME International

    Mihai Diaconeasa

  79. Benchmark Study of XFTA and SCRAM Fault Tree Solvers Using Synthetically Generated Fault Trees Models

    Article • October 2022, ASME International

    Mihai Diaconeasa

  80. Preliminary Siting, Operations, and Transportation Considerations for Licensing Fission Batteries in the United States

    Article • Eng—Advances in Engineering, September 2022, MDPI AG

    Mihai Diaconeasa

  81. Implementing Probabilistic Design Methods in Plant Systems Design

    Article • July 2022, ASME International

    Mihai Diaconeasa

  82. A framework to implement human reliability analysis during early design stages of advanced reactors

    Article • Progress in Nuclear Energy, April 2022, Elsevier

    Mihai Diaconeasa

  83. A human reliability assessment model for the cognitive process of MASS shore-based operator applied, to dynamic probabilistic risk assessment platform

    Article • January 2022, Research Publishing Services

    Mihai Diaconeasa

  84. Investigating the Applicability of Human Reliability Analysis Methods During Early Design Stages of Non-Light-Water Nuclear Power Plants

    Article • SSRN Electronic Journal, January 2022, Elsevier

    Mihai Diaconeasa

  85. Pool Inlet Loca Safety Analysis in Support of the Emergency Core Spray System Success Criteria Development of the Pulstar Research Reactor

    Article • SSRN Electronic Journal, January 2022, Elsevier

    Mihai Diaconeasa

  86. A Quantitative Approach to Assess the Likelihood of Supply Chain Shortages

    Article • November 2021, ASME International

    Mihai Diaconeasa

  87. Demonstration of a Limited Scope Probabilistic Risk Assessment for Autonomous Warehouse Robots With OpenPRA

    Article • November 2021, ASME International

    Mihai Diaconeasa

  88. Evaluating the Implementation of Distributed Ledger Technology for the Licensing and Regulation of Nuclear Power Plants

    Article • November 2021, ASME International

    Mihai Diaconeasa

  89. On the Modeling of Wildfires-Induced Release and Atmospheric Dispersion in Radioactively Contaminated Regions

    Article • November 2021, ASME International

    Mihai Diaconeasa

  90. On the Use of Probabilistic Risk Assessment for the Protection of Small Modular Reactors Against Terrorist Attacks

    Article • November 2021, ASME International

    Mihai Diaconeasa

  91. Verification Study of the Nuclear PRA for the Mars 2020 Mission Following Accidental Orbital Re-Entry

    Article • November 2021, ASME International

    Mihai Diaconeasa

  92. A Critical Look at the Need for Performing Multi-Hazard Probabilistic Risk Assessment for Nuclear Power Plants

    Article • Eng—Advances in Engineering, October 2021, MDPI AG

    Mihai Diaconeasa

  93. On the Use of the Accident Dynamic Simulator Method in Ship Collision Accident Analysis

    Article • July 2021, ASME International

    Mihai Diaconeasa

  94. Method and software platform for electronic COTS parts reliability estimation in space applications

    Article • Proceedings of the Institution of Mechanical Engineers Part O Journal of Risk and Reliability, March 2021, SAGE Publications

    Mihai Diaconeasa

  95. A Hybrid Methodology for Model-Based Probabilistic Resilience Evaluation of Dynamic Systems

    Article • November 2020, ASME International

    Mihai Diaconeasa

  96. On the Use of the Accident Dynamic Simulator Method in Ship Collision Accident Analysis

    Article • November 2020, ASME International

    Mihai Diaconeasa

  97. A Comparative Assessment of Collision Risk of Manned and Unmanned Vessels

    Article • Journal of Marine Science and Engineering, October 2020, MDPI AG

    Mihai Diaconeasa

  98. On the Use of the Hybrid Causal Logic Methodology in Ship Collision Risk Assessment

    Article • Journal of Marine Science and Engineering, June 2020, MDPI AG

    Mihai Diaconeasa

  99. A Dynamic Pipeline Network Health Assessment Software Platform for Optimal Risk-Based Prioritization of Inspection, Structural Health Monitoring, and Proactive Management

    Article • November 2019, ASME International

    Mihai Diaconeasa

  100. A Numerical and Experimental Study Supporting a Methodology for Live Monitoring, Leak Detection, and Automatic Response in Water Pipelines

    Article • November 2019, ASME International

    Mihai Diaconeasa

  101. A Smart Pipeline Monitoring and Emergency Response System Using Web Services

    Article • November 2019, ASME International

    Mihai Diaconeasa

  102. Model-Based Resilience Assessment Framework for Autonomous Systems

    Article • November 2019, ASME International

    Mihai Diaconeasa

  103. Branching rules and quantification based on human behavior in the ADS-IDAC dynamic PRA platform

    Article • June 2018, Taylor & Francis

    Mihai Diaconeasa

  104. HYPRA

    Article • June 2018, Taylor & Francis

    Mihai Diaconeasa

  105. Optimization of Deep Borehole Systems for HLW Disposal

    Article • September 2015, Office of Scientific and Technical Information (OSTI)

    Mihai Diaconeasa

  106. Magnetic-field-induced nematic–nematic phase separation and droplet formation in colloidal goethite

    Article • Journal of Physics Condensed Matter, April 2011, Institute of Physics Publishing

    Dr Ivan Dozov, Mihai Diaconeasa

  107. Onsager Revisited: Magnetic Field Induced Nematic−Nematic Phase Separation in Dispersions of Goethite Nanorods

    Article • The Journal of Physical Chemistry Letters, July 2010, American Chemical Society (ACS)

    Andrei Petukhov, Mihai Diaconeasa