Pradeep Ramuhalli Group Leader, Modern Nuclear I&C Group, Nuclear Energy and Fuel Cycle Division Contact RAMUHALLIP@ORNL.GOV All Publications Digital Twins for Nuclear Power Plants and Facilities Machine learning for ultrasonic nondestructive examination of welding defects: A systematic review Uncertainty aware anomaly detection to predict errant beam pulses in the Oak Ridge Spallation Neutron Source accelerator Ultrasonic nondestructive diagnosis of lithium-ion batteries with multiple frequencies Development of a BWR System Fault Simulator Using TRANSFORM/Modelica Regulatory Requirements, Guidance, and Review of Digital Twins Laser Doppler vibrometry for piezoelectric coefficient ( d33 ) measurements in irradiated aluminum nitride How Digital Twins May Be Used in Design and Operations... A Methodology for Online Sensor Recalibration Application of Convolutional and Feedforward Neural Networks for Fault Detection in Particle Accelerator Power Systems Irradiation-induced Degradation of Surface Acoustic Wave Devices Fabricated on Bulk AlN... Machine learning of ultrasonic data for expansion prediction of concrete with alkali-silica reaction Status Report on Regulatory Criteria Applicable to the Use of Digital Twins Consolidated Hydropower Data Repository: Value and Opportunities Physics-informed neural networks for identification of material properties using standing waves Analytical modeling of the evolution of the nonlinearity parameter of sensitized stainless steel... DEVELOPMENT OF ULTRASONIC DENSIMETER AND VISCOMETER FOR FLUID CHARACTERIZATION... Prognostics and Health Management in Nuclear Power Plants: An Updated Method-Centric Review With Special Focus on Data-Driven Methods Nuclear Power Prognostic Model Assessment For Component Health Monitoring Estimation of Sensor Measurement Errors in Reactor Coolant Systems Using Multi-Sensor Fusion Electromechanical response of piezoelectric thin films subjected to large strain Development of Prognostic Models Using Plant Asset Data Development and Validation of Quantitative Model-Based Image Reconstruction for NDE of Reinforced Steel-Lined Concrete Structures: Kal-El FY 2020 Sensor Drift Estimation for Reactor Systems by Fusing Multiple Sensor Measurements Sensor Error Estimation for Reactor Coolant System with Generalization Error Equations Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 Next page ›â¶Äº Last page Last » Key Links Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Advanced Reactor Engineering and Development Section Modern Nuclear Instrumentation and Controls Group Energy Science and Technology Directorate Water Power Program Artificial Intelligence (AI) Initiative
Research Highlight Adaptive Single Parameter Total Variation Regularization for Derivative Estimation
