Search by property

This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML19325C903  + (NUREG/CR-7258 Technical Manual and Users Guide for Mildos, Version 4.1)
• NUREG/CR-7259, Mildos Version 4.1 Computational Verification Report  + (NUREG/CR-7259 Mildos Version 4.1 Computational Verification Report)
• ML19325C464  + (NUREG/CR-7259 Mildos Version 4.1 Computational Verification Report)
• ML19123A127  + (NUREG/CR-7260, Cfd Validation of Vertical Dry Cask Storage System)
• NUREG/CR-7262, State-of-the-Art Reactor Consequence Analyses Project Uncertainty Analysis of the Unmitigated Short-Term Station Blackout of the Surry Power Station  + (NUREG/CR-7262, State-of-the-Art Reactor Consequence Analyses Project Uncertainty Analysis of the Unmitigated Short-Term Station Blackout of the Surry Power Station)
• NUREG/CR-7263, NDE Reliability Issues for the Examination of CASS Components  + (NUREG/CR-7263 NDE Reliability Issues for the Examination of CASS Components)
• NUREG/CR-7265 Volume 1, Phenomena Identification and Ranking Technique (PIRT) Exercise for Ranking Low-Power Shutdown Plant Operating States and Outage Types, Chapters 1-7  + (NUREG/CR-7265 Vol 1, Phenomena Identification and Ranking Technique (PIRT) Exercise for Ranking Low-Power Shutdown Plant Operating States and Outage Types, Chapters 1-7)
• NUREG/CR-7265 Volume 2, Phenomena Identification and Ranking Technique (PIRT) Exercise for Ranking Low-Power Shutdown Plant Operating States and Outage Types Appendices A-K  + (NUREG/CR-7265 Vol 2 Phenomena Identification and Ranking Technique (PIRT) Exercise for Ranking Low-Power Shutdown Plant Operating States and Outage Types Appendices A-K)
• ML20281A614  + (NUREG/CR-7265, Vol. 1 & Vol. 2 Phenomena Identification and Ranking Technique (PIRT) Exercise for Ranking Low-Power Shutdown Plant Operating States and Outage Types)
• NUREG/CR-7266, Melcor Modeling of Accident Scenarios at a Facility for Aqueous Reprocessing of Spent Nuclear Fuel  + (NUREG/CR-7266, Melcor Modeling of Accident Scenarios at a Facility for Aqueous Reprocessing of Spent Nuclear Fuel)
• ML24173A152  + (NUREG/CR-7267, Default Parameter Values and Distribution in RESRAD-ONSITE V7.2, RESRAD-BUILD V3.5, and RESRAD-OFFSITE V4.0 Computer Codes)
• NUREG/CR-7268 Volume 2, Users Manual for RESRAD-Offsite Code Version 4 - Users Guide for RESRAD-Offsite  + (NUREG/CR-7268 Vol 2 Users Manual for RESRAD-Offsite Code Version 4 - Users Guide for RESRAD-Offsite)
• ML21091A159  + (NUREG/CR-7268, Vol 1, Users Manual for RESRAD-OFFSITE Code Version 4 -- Methodology and Models Used in RESRAD-OFFSITE Code)
• ML20070M158  + (NUREG/CR-7269, Enhancing Guidance for Evacuation Time Estimate Studies)
• ML22294A091  + (NUREG/CR-7270, Technical Bases for Consequence Analyses Using Maccs (Melcor Accident Consequence Code System))
• NUREG/CR-7271, Application of Point Precipitation Frequency Estimates to Watersheds  + (NUREG/CR-7271, Application of Point Precipitation Frequency Estimates to Watersheds)
• NUREG/CR-7272, NRC ATWS-I Stability Tests with Downskew Axial Power Profile: Kathy Test Series STS123  + (NUREG/CR-7272, NRC ATWS-I Stability Tests with Downskew Axial Power Profile: Kathy Test Series STS123)
• 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)