Michael Muhlheim R&D Staff Contact 865.574.0386 | MUHLHEIMMD@ORNL.GOV All Publications 91°µÍø's Strategic Research and Development Insights for Digital Twins Status Report on Regulatory Criteria Applicable to the Use of Artificial Intelligence (AI) and Machine Learning (ML) Technical Specification Surveillance Interval Extension Using Self-Diagnostics Risk-Informing Critical Digital Assets (CDAs) for Nuclear Power Systems... A Risk-Informed Assessment of Operational Options for Successfully Avoiding a Trip Setpoint Criteria for Determining the Safety of Wireless Technologies at Nuclear Power Plants Assessment of Applicability of Standards Endorsed by Regulatory Guides to Molten Salt Reactors Criteria for Determining the Safety of Wireless Technologies at Nuclear Power Plants... Regulatory Requirements, Guidance, and Review of Digital Twins How Digital Twins May Be Used in Design and Operations... A Methodology for Online Sensor Recalibration Status Report on Regulatory Criteria Applicable to the Use of Digital Twins Molten Salt Reactor Fundamental Safety Function PIRT REGULATORY REQUIREMENTS, GUIDANCE, AND REVIEW OF EMBEDDED DIGITAL DEVICES IN SAFETY SYSTEMS OPERATING EXPERIENCE AND ITS RELATIONSHIP TO EMBEDDED DIGITAL DEVICES IN SAFETY SYSTEMS An Overview of the Integrated Energy System Investigation of the Eastman Chemical Company Kingsport, Tennessee, Facility Integrated Energy System Investigation for the Eastman Chemical Co. Kingsport, TN Facility Proposed guidance for preparing and reviewing a molten salt non-power production or utilization facility application Development of an Obsolescence Cost Model for Nuclear Power Plants Molten Salt Reactor Initiating Event and Licensing Basis Event Workshop Summary A New Layer to the PRA: Operational Performance Risk Assessment... Licensing process for upgrading I&C systems at nonpower production or utilization facilities (NPUFs) Simulation-Based Testing for Instrumentation and Control Systems... Operational Performance Risk Assessment in Support of A Supervisory Control System A QUALITATIVE ASSESSMENT OF CURRENT CCF GUIDANCE BASED ON A REVIEW OF SAFETY SYSTEM DIGITAL IMPLEMENTATION CHANGES WITH EVOLVING TECHNOLOGY Pagination Current page 1 Page 2 Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae 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
