Nuclear Engineering

Impact of ionization peak location on measured opaqueness in DIII-D H-mode plasmas

Nuclear Fusion.

The Development, Implementation, and Application of a Probabilistic Risk Assessment Framework to Evaluate Supply Chain Shortages

Pandit, P., Earthperson, A., & Diaconeasa, M. A. (2025, August 14).

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 610–619.

Analysis of Radiological Release From Fueled Irradiation Experiments During Manual Handling

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 743–749.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 381–390.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 980–989.

Design and Implementation of a Distributed Queueing System for OpenPRA

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 400–408.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 300–309.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 1059–1068.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 1042–1051.

Evaluation of Recent Advances in Multi-Hazard Risk Assessment

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 600–609.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 362–371.

Git Application for Configuration Control Programs of Advanced Nuclear Power Plants

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 885–894.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 433–443.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 1079–1085.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 724–733.

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

Npj Clean Energy, 1(1).

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 104–113.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 48–56.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 516–529.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 856–867.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 1052–1058.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 562–572.

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

19th International Conference on Probabilistic Safety Assessment and Analysis (PSA 2025), 372–380.

Atomic-scale modeling assessing the impact of defects on the thermal conductivity of UN

PROGRESS IN NUCLEAR ENERGY, 189.