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List of results

• NUREG/CR-7273, Developing a Technical Basis for Embedded Digital Devices and Emerging Technologies  + (NUREG/CR-7273, Developing a Technical Basis for Embedded Digital Devices and Emerging Technologies)
• ML20357A056  + (NUREG/CR-7274 Validation of a Computational Fluid Dynamics Method Using Horizontal Dry Cask Simulator Data)
• NUREG/CR-7275, Jet Impingement in High-Energy Piping Systems  + (NUREG/CR-7275 Jet Impingement in High-Energy Piping Systems)
• ML23095A378  + (NUREG/CR-7276, Primary Water Stress Corrosion Cracking of High-Chromium Nickel-Base Welds - 2018)
• ML23095A385  + (NUREG/CR-7277, Primary Water Stress Corrosion Cracking of High-Chromium Nickel-Base Welds at or Near Interfaces – 2020)
• NUREG/CR-7278, Technical Basis for the Use of Probabilistic Fracture Mechanics in Regulatory Applications - Final  + (NUREG/CR-7278, Technical Basis for the Use of Probabilistic Fracture Mechanics in Regulatory Applications - Final)
• ML22053A021  + (NUREG/CR-7279, Rev. 1, Research to Develop Flood Barrier Testing Strategies for Nuclear Power Plants)
• ML21202A265  + (NUREG/CR-7280, Review of Radiation-Induced Concrete Degradation and Potential Implications for Structures Exposed to High, Long-Term Radiation Levels in Nuclear Power Plants)
• NUREG/CR-7281, Radiation Evaluation Methodology for Concrete Structures  + (NUREG/CR-7281, Radiation Evaluation Methodology for Concrete Structures)
• NUREG/CR-7282, Review of Accident Tolerant Fuel Concepts with Implications to Severe Accident Progression and Radiological Releases  + (NUREG/CR-7282, Review of Accident Tolerant Fuel Concepts with Implications to Severe Accident Progression and Radiological Releases)
• ML21210A331  + (NUREG/CR-7283, Phenomena Identification Ranking Tables for Accident Tolerant Fuel Designs Applicable to Severe Accident Conditions)
• NUREG/CR-7284, Scale 6.2 Lattice Physics Performance Assessment  + (NUREG/CR-7284, Scale 6.2 Lattice Physics Performance Assessment)
• ML21252A104  + (NUREG/CR-7285, Nonradiological Health Consequences from Evacuation and Relocation)
• NUREG/CR-7286, Reactor Pressure Vessel Fluence Evaluation Methodology for Extended Beltline Locations  + (NUREG/CR-7286, Reactor Pressure Vessel Fluence Evaluation Methodology for Extended Beltline Locations)
• ML23207A195  + (NUREG/CR-7287, Numerical Modeling of Local Intense Precipitation Processes)
• NUREG/CR-7288 Volume 1, Evaluation of In-Service Radon Barriers Over Uranium Mill Tailings Disposal Facilities  + (NUREG/CR-7288 Volume 1, Evaluation of In-Service Radon Barriers Over Uranium Mill Tailings Disposal Facilities)
• NUREG/CR-7288 Volume 2, Evaluation of In-Service Radon Barriers Over Uranium Mill Tailings Disposal Facilities - Appendices  + (NUREG/CR-7288 Volume 2, Evaluation of In-Service Radon Barriers Over Uranium Mill Tailings Disposal Facilities - Appendices)
• NUREG/CR-7289, Nuclear Data Assessment for Advanced Reactors  + (NUREG/CR-7289, Nuclear Data Assessment for Advanced Reactors)
• NUREG/CR-7290, Convection-Permitting Modeling for Intense Precipitation Processes  + (NUREG/CR-7290, Convection-Permitting Modeling for Intense Precipitation Processes)
• NUREG/CR-7291, Assessments on Eddy Current Detection of Cracking Near Volumetric Indications in Steam Generator Tubes  + (NUREG/CR-7291 - Assessments on Eddy Current Detection of Cracking Near Volumetric Indications in Steam Generator Tubes)
• ML21208A003  + (NUREG/CR-7291, ANL-18/41, Assessments of Eddy Current Detection of Cracking Near Volumetric Indications in Steam Generator Tubes)
• NUREG/CR-7293, the Price-Anderson Act: 2021 Report to Congress, Public Liability Insurance and Indemnity Requirements for an Evolving Commercial Nuclear Industry  + (NUREG/CR-7293 the Price-Anderson Act: 2021 Report to Congress, Public Liability Insurance and Indemnity Requirements for an Evolving Commercial Nuclear Industry)
• ML22042A662  + (NUREG/CR-7294, Exploring Advanced Computational Tools and Techniques with Artificial Intelligence and Machine Learning in Operating Nuclear Plants)
• NUREG/CR-7295, Human Factors in Nondestructive Examination  + (NUREG/CR-7295, Human Factors in Nondestructive Examination)
• NUREG/CR-7296, Multi-Mechanism Flood Hazard Assessment: Critical Review of Current Practice and Approaches and Example Use Studies  + (NUREG/CR-7296, Multi-Mechanism Flood Hazard Assessment: Critical Review of Current Practice and Approaches and Example Use Studies)

• NUREG/CR-7299, Fuel Qualification for Molten Salt Reactors  + (NUREG/CR-7299, Fuel Qualification for Molten Salt Reactors)

• ML23237B247  + (NUREG/CR-7300, Radiation Accident Dose and Simulated Loss-of-Coolant Accident Test of Low Voltage Cables)
• NUREG/CR-7301, PNNL-33732, Ultrasonic Modeling and Simulation for Nuclear Nondestructive Evaluation  + (NUREG/CR-7301, PNNL-33732, Ultrasonic Modeling and Simulation for Nuclear Nondestructive Evaluation)
• NUREG/CR-7302, Revision 1, Updated Recommendations Related to Spent Fuel Transport and Dry Storage Shielding Analyses  + (NUREG/CR-7302, Revision 1, Updated Recommendations Related to Spent Fuel Transport and Dry Storage Shielding Analyses)
• NUREG/CR-7303, Validating Actinides and Fission Products for Burnup Credit Criticality Safety Analyses – Nuclide Compositions Prediction with Extended Validation Basis  + (NUREG/CR-7303, Validating Actinides and Fission Products for Burnup Credit Criticality Safety Analyses – Nuclide Compositions Prediction with Extended Validation Basis)
• NUREG/CR-7304, Evaluating Flaw Detectability Under Limited-Coverage Conditions  + (NUREG/CR-7304, Evaluating Flaw Detectability Under Limited-Coverage Conditions)
• ML23214A065  + (NUREG/CR-7305, Metal Fuel Qualification: Fuel Assessment Using NRC NUREG-2246, Fuel Qualification for Advanced Reactors)
• NUREG/CR-7306, Revision 1, Fuel Assembly and Irradiation Parametric Study for Extended-Enrichment and High-Burnup Light-Water Reactor Spent Nuclear Fuel in Dry Storage Casks and Transportation Packages  + (NUREG/CR-7306, Revision 1, Fuel Assembly and Irradiation Parametric Study for Extended-Enrichment and High-Burnup Light-Water Reactor Spent Nuclear Fuel in Dry Storage Casks and Transportation Packages)
• ML24155A058  + (NUREG/CR-7307,Phenomena Identification and Ranking Tables on High Burnup Fuel Fragmentation, Relocation, Dispersal, and Its Consequences for Design-Basis Accidents in Pressurized- and Boiling-Water Reactors)
• NUREG/CR-7308, Sensitivity/Uncertainty Methods for Nuclear Criticality Safety Validation  + (NUREG/CR-7308, Sensitivity/Uncertainty Methods for Nuclear Criticality Safety Validation)
• NUREG/CR-7309, Validation Studies for High Burnup and Extended Enrichment Fuels in Burnup Credit Criticality Safety Analyses  + (NUREG/CR-7309, Validation Studies for High Burnup and Extended Enrichment Fuels in Burnup Credit Criticality Safety Analyses)
• NUREG/CR-7310, Spent Fuel Storage and Transportation of Accident Tolerant Fuel Concepts  + (NUREG/CR-7310, Spent Fuel Storage and Transportation of Accident Tolerant Fuel Concepts)
• NUREG/CR-7311, Determination of Bias and Bias Uncertainty for Criticality Safety Computational Methods  + (NUREG/CR-7311, Determination of Bias and Bias Uncertainty for Criticality Safety Computational Methods)
• ML13127A331  + (NUREG/CR-XXXX PNNL-XXXXX Ultrasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna Unit 2 Control Rod Drive Mechanism Nozzle 63 with Destructive Validation, 5.4 Through End)
• ML13219A031  + (NUREG/CR-XXXX PNNL-XXXXX Ultrasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna Unit 2 Control Rod Drive Mechanism Nozzle 63 with Destructive Validation)
• ML13127A382  + (NUREG/CR-XXXX PNNL-XXXXX Ultrasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna Unit 2 Control Rod Drive Mechanism Nozzle 63 with Destructive Validation, Cover Through 5-14)
• ML21313A361  + (NUREG/CR-XXXX, Fuel Qualification for Molten Salt Reactors, Draft Report for Comment)
• ML18086A425  + (NUREG/CR7135 Draft for Public Comments - Resolution of Comments)
• ML15278A056  + (NUREG/IA-0456 International Agreement Report Bepu Analysis and Benchmark with Iist 2% SBLOCA Experiment Using Trace/Dakota)
• ML20156A309  + (NUREG/IA-0468, Revision 1, Validation of RELAP5 Model of Ringhals 4 Against a Load Step Test at Uprated Power)
• ML21295A537  + (NUREG/IA-0470, Volume 2, Nuclear Regulatory Authority Experimental Program to Characterize and Understand High Energy Arcing Fault (HEAF) Phenomena; Basic Arc Test Experimental Data)
• ML18302A011  + (NUREG/IA-0483, International Agreement Report - Loss of Flow Analysis of Maanshan Nuclear Power Plant with RELAP5/SNAP)
• ML18312A390  + (NUREG/IA-0484, International Agreement Report: Pactel Small Break LOCA Experiment SBL-30 Calculation with Trace Code)
• ML18360A206  + (NUREG/IA-0485, International Agreement Report - Trace VVER-440/V-213 Model Validation)
• ML18323A182  + (NUREG/IA-0486 - International Agreement Report - Simulation of the G3.1 Experiment at Pkl Facility Using RELAP5/Mod3.3)
• ML19015A027  + (NUREG/IA-0487 International Agreement Report - Simulation of the PKL-G7.1 Experiment in a Westinghouse Nuclear Power Plant Using RELAP5/Mod3.3)