Mihai A Diaconeasa

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

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

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

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

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

WATER SCIENCE AND ENGINEERING, 17(4), 417–424.

Aalo Atomics' High Level Licensing Strategy

Advanced Reactor Safety (ARS), 358–365.

Addressing Uncertainties Across All Design Stages of Advanced Reactors Development

Advanced Reactor Safety (ARS), 268–277.

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

Advanced Reactor Safety (ARS), 532–541.

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

Advanced Reactor Safety (ARS), 430–438.

Enhancing the SAPHIRE Solve Engine: Initial Progress and Efforts

Advanced Reactor Safety (ARS), 542–551.

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

Advanced Reactor Safety (ARS), 573–582.

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

Reliability Engineering & System Safety.

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

Advanced Reactor Safety (ARS), 81–90.

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

Advanced Reactor Safety (ARS), 552–561.

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

Advanced Reactor Safety (ARS), 91–99.

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

Advanced Reactor Safety (ARS), 156–165.

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

ADVANCED ENGINEERING INFORMATICS, 62.

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

Advanced Reactor Safety (ARS), 300–309.

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

Advanced Reactor Safety (ARS), 562–572.

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

Advanced Reactor Safety (ARS), 176–183.

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

Advanced Reactor Safety (ARS), 4–15.

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

Advanced Reactor Safety (ARS), 410–419.

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

Advanced Reactor Safety (ARS), 310–318.

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

Advanced Reactor Safety (ARS), 400–409.

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

ENG, 4(2), 1655–1683.

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

Progress in Nuclear Energy.

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

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 12–21.

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

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 334–343.

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

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 262–271.

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

Earthperson, A., & Diaconeasa, M. A. (2023, July 6).

High-Performance Computing Implementation for ADS-IDAC

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 292–301.

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

DRONES, 7(8).

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

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 757–766.

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

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

Volume 13: Research Posters; Safety Engineering, Risk and Reliability Analysis, 13.

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

PROGRESS IN NUCLEAR ENERGY, 161.

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

Volume 13: Research Posters; Safety Engineering, Risk and Reliability Analysis. Presented at the ASME 2023 International Mechanical Engineering Congress and Exposition.

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

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 134–140.

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

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 452–459.

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

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 150–158.

Motion Prediction of Tugboats Using Hidden Markov Model

2023 7th International Conference on Transportation Information and Safety (ICTIS), 621–627.

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

NUCLEAR ENGINEERING AND DESIGN, 403.

Pool inlet LOCA safety analysis in support of the emergency core spray system success criteria development of the PULSTAR research reactor (vol 403, 112163, 2023)

Farag, A. S., Alzahrani, Y. A., & Diaconeasa, M. A. (2023, July). NUCLEAR ENGINEERING AND DESIGN, Vol. 408.

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

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 40–49.

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

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 514–520.

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

Volume 13: Research Posters; Safety Engineering, Risk and Reliability Analysis.

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

Volume 13: Research Posters; Safety Engineering, Risk and Reliability Analysis.

Quantifying the Likelihood of Nuclear Supply Chain Shortage Risk

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 668–674.

Risk Analysis of Various Design Architectures for High Safety-significant Safety-related Digital Instrumentation and Control Systems of Nuclear Power Plants during Accident Scenarios

https://www.osti.gov/biblio/1986002

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

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 910–919.

Xe-100 PRA Event Sequence Modeling Framework

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 640–648.

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

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 160–169.

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

PROGRESS IN NUCLEAR ENERGY, 146.

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

8th International Symposium on Reliability Engineering and Risk Management, 202–209.

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

Volume 6: Energy.

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

Volume 9: Mechanics of Solids, Structures, and Fluids; Micro- and Nano-Systems Engineering and Packaging; Safety Engineering, Risk, and Reliability Analysis; Research Posters.

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

Volume 9: Mechanics of Solids, Structures, and Fluids; Micro- and Nano-Systems Engineering and Packaging; Safety Engineering, Risk, and Reliability Analysis; Research Posters, 9.

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

Grimmeisen, P., Karimov, A., Diaconeasa, M. A., & Morozov, A. (2022, January). Volume 13: Safety Engineering, Risk, and Reliability Analysis; Research Posters, Vol. 13.

Implementing Probabilistic Design Methods in Plant Systems Design

Volume 1: Codes and Standards.

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

SSRN Electronic Journal.

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

Polat, D., & Diaconeasa, M. A. (2022, January). Volume 13: Safety Engineering, Risk, and Reliability Analysis; Research Posters, Vol. 13.

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

Polat, B., & Diaconeasa, M. A. (2022, January). Volume 13: Safety Engineering, Risk, and Reliability Analysis; Research Posters, Vol. 13.

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

SSRN Electronic Journal.

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

Eng.

Probabilistic Methods for Cyclical and Coupled Systems with Changing Failure Rates

Yang Hui Otani, C. M. ; Christian, R. ; Prescott, S. R. ; Diaconeasa, M. ; & Earthperson, A. (2022, April). https://www.osti.gov/biblio/1885929

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

Eng, 2(4), 454–467.

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

Morozov, A., Diaconeasa, M. A., & Steurer, M. (2021, February). Volume 14: Safety Engineering, Risk, and Reliability Analysis, Vol. 14.

A Quantitative Approach to Assess the Likelihood of Supply Chain Shortages

Volume 13: Safety Engineering, Risk, and Reliability Analysis; Research Posters, 13.

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

Volume 8B: Energy, 8B-2021.

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

Proceedings of the Institution of Mechanical Engineers, Part O: Journal of Risk and Reliability, 232(5), 744–760.

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

Shi, S., Wang, T., & Diaconeasa, M. (2021, July). (Vol. 7). Vol. 7.

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

A Comparative Assessment of Collision Risk of Manned and Unmanned Vessels

JOURNAL OF MARINE SCIENCE AND ENGINEERING, 8(11).

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

Chalgham, W., Diaconeasa, M., Wu, K.-Y., & Mosleh, A. (2020, January). Volume 13: Safety Engineering, Risk, and Reliability Analysis, Vol. 13.

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

Chalgham, W., Diaconeasa, M., Gottumukkala, R., & Seibi, A. (2020, January). Volume 13: Safety Engineering, Risk, and Reliability Analysis, Vol. 13.

A Smart Pipeline Monitoring and Emergency Response System Using Web Services

Chalgham, W., Diaconeasa, M., Elgazzar, K., & Seibi, A. (2020, January). Volume 13: Safety Engineering, Risk, and Reliability Analysis, Vol. 13.

Model-Based Resilience Assessment Framework for Autonomous Systems

Diaconeasa, M. A., Mosleh, A., Morozov, A., & Tai, A. T. (2020, January). Volume 13: Safety Engineering, Risk, and Reliability Analysis, Vol. 13.

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

Volume 14: Safety Engineering, Risk, and Reliability Analysis.

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

JOURNAL OF MARINE SCIENCE AND ENGINEERING, 8(7).

A survey on autonomous vehicles interactions with human and other vehicles

PSAM 2018 - Probabilistic Safety Assessment and Management. http://www.scopus.com/inward/record.url?eid=2-s2.0-85063138117&partnerID=MN8TOARS

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

Diaconeasa, M. A., & Mosleh, A. (2018, June). Safety and Reliability – Safe Societies in a Changing World, pp. 1749–1756.

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

Safety and Reliability - Safe Societies in a Changing World - Proceedings of the 28th International European Safety and Reliability Conference, ESREL 2018, 1749–1756. http://www.scopus.com/inward/record.url?eid=2-s2.0-85058130438&partnerID=MN8TOARS

Development of a software platform for pipeline health monitoring and management

PSAM 2018 - Probabilistic Safety Assessment and Management. http://www.scopus.com/inward/record.url?eid=2-s2.0-85063123667&partnerID=MN8TOARS

Discrete dynamic event tree uncertainty quantification in the ADS-IDAC dynamic PSA software platform

PSAM 2018 - Probabilistic Safety Assessment and Management. http://www.scopus.com/inward/record.url?eid=2-s2.0-85063155237&partnerID=MN8TOARS

HYPRA

Diaconeasa, M. A., & Mosleh, A. (2018, June). Safety and Reliability – Safe Societies in a Changing World, pp. 1757–1763.

HYPRA: A hybrid static-dynamic PRA software platform

Safety and Reliability - Safe Societies in a Changing World - Proceedings of the 28th International European Safety and Reliability Conference, ESREL 2018, 1757–1766. http://www.scopus.com/inward/record.url?eid=2-s2.0-85058090465&partnerID=MN8TOARS

Performing an accident sequence precursor analysis with the ADS-IDAC dynamic PSA software platform

PSAM 2018 - Probabilistic Safety Assessment and Management. http://www.scopus.com/inward/record.url?eid=2-s2.0-85063132484&partnerID=MN8TOARS

The impact of time-varying operating parameters on the corrosion rate and depth of gas pipelines

PSAM 2018 - Probabilistic Safety Assessment and Management. http://www.scopus.com/inward/record.url?eid=2-s2.0-85063152604&partnerID=MN8TOARS

The ADS-IDAC dynamic platform with dynamically linked system fault trees

International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017, 1, 482–491. http://www.scopus.com/inward/record.url?eid=2-s2.0-85047838434&partnerID=MN8TOARS

Optimization of Deep Borehole Systems for HLW Disposal

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

Journal of Physics: Condensed Matter, 23(19), 194108.

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

The Journal of Physical Chemistry Letters, 1(14), 2174–2178.