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

• ML110100377  + (NUREG/CR-7027, Degradation of LWR Core Internal Materials Due to Neutron Irradiation)
• ML18215A300  + (NUREG/CR-7028, Vol. 1, Engineered Covers for Waste Containment: Changes in Engineering Properties and Implications for Long-Term Performance Assessment)
• NUREG/CR-7103 Volume 4, Pacific Northwest National Laboratory Investigation of Stress Corrosion Cracking in Nickel-Base Alloys: Behavior of Alloy 152 and 52 Welds  + (NUREG/CR-7103, Vol. 4, Pacific Northwest National Laboratory Investigation of Stress Corrosion Cracking in Nickel-Base Alloys: Behavior of Alloy 152 and 52 Welds)
• NUREG/CR-7110 Volume 1, Rev 1 State-of-the-Art Reactor Consequence Analyses Project: Peach Bottom Integrated Analysis  + (NUREG/CR-7110 Vol 1 Rev 1 State-of-the-Art Reactor Consequence Analyses Project: Peach Bottom Integrated Analysis)
• NUREG/CR-7110 Volume 2, Rev 1 State-of-the-Art Reactor Consequence Analyses Project Volume 2: Surry Integrated Analysis  + (NUREG/CR-7110 Vol 2 Rev 1 State-of-the-Art Reactor Consequence Analyses Project Volume 2: Surry Integrated Analysis)
• ML120260681  + (NUREG/CR-7110 Vol 2 State-of-the-Art Reactor Consequence Analyses Project: Surry Integrated Analysis)
• NUREG/CR-7131, Review of Probable Maximum Precipitation Procedures and Databases Used to Develop Hydrometeorological Reports  + (NUREG/CR-7131, Review of Probable Maximum Precipitation Procedures and Databases Used to Develop Hydrometeorological Reports)
• NUREG/CR-7132, Application of Radar-Rainfall Estimates to Probable Maximum Precipitation in the Carolinas  + (NUREG/CR-7132, Application of Radar-Rainfall Estimates to Probable Maximum Precipitation in the Carolinas)
• NUREG/CR-7133, Synthesis of Extreme Storm Rainfall and Probable Maximum Precipitation in the Southeastern U.S. Pilot Region  + (NUREG/CR-7133, Synthesis of Extreme Storm Rainfall and Probable Maximum Precipitation in the Southeastern U.S. Pilot Region)
• NUREG/CR-7153 Volume 1, Vol 4 Errata Expanded Materials Degradation Assessment (Emda)  + (NUREG/CR-7153, Vol. 1, Vol 4 Errata Expanded Materials Degradation Assessment (Emda))
• NUREG/CR-7154 Volume 1, Risk Informing Emergency Preparedness Oversight: Evaluation of Emergency Action Levels - a Pilot Study of Peach Bottom, Surry and Sequoyah (Main Report, Appendices a and B)  + (NUREG/CR-7154 Vol 1 Risk Informing Emergency Preparedness Oversight: Evaluation of Emergency Action Levels - a Pilot Study of Peach Bottom, Surry and Sequoyah (Main Report, Appendices a and B))
• NUREG/CR-7154 Volume 2, Risk Informing Emergency Preparedness Oversight: Evaluation of Emergency Action Levels - a Pilot Study of Peach Bottom, Surry and Sequoyah (Appendices C - F)  + (NUREG/CR-7154 Vol. 2 Risk Informing Emergency Preparedness Oversight: Evaluation of Emergency Action Levels - a Pilot Study of Peach Bottom, Surry and Sequoyah (Appendices C - F))
• NUREG/CR-7155, State-of-the-Art Reactor Consequence Analyses Project. Uncertainty Analysis of the Unmitigated Long-Term Station Blackout of the Peach Bottom Atomic Power Station  + (NUREG/CR-7155, State-of-the-Art Reactor Consequence Analyses Project. Uncertainty Analysis of the Unmitigated Long-Term Station Blackout of the Peach Bottom Atomic Power Station)
• ML13189A145  + (NUREG/CR-7155, State-of-the-Art Reactor Consequence Analyses Project, Uncertainty Analysis of the Unmitigated Long-Term Station Blackout of the Peach Bottom, Draft Report)
• ML16210A459  + (NUREG/CR-7219, Cladding Behavior During Postulated Loss-of- Coolant Activities)
• ML18018A562  + (NUREG/CR-7226, Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Base Welds Near Dissimilar Metal Weld Interfaces)
• ML18022A139  + (NUREG/CR-7233, Developing a Bayesian Belief Network Model for Quantifying the Probability of Software Failure of a Protection System)
• ML18012A048  + (NUREG/CR-7238, Guidance Document: Conducting Palcoliquefaction Studies for Earthquake Source Characterization)
• NUREG/CR-7239, Review of Exemptions and General Licenses for Fissile Material in 10 CFR 71  + (NUREG/CR-7239, Review of Exemptions and General Licenses for Fissile Material in 10 CFR 71)
• NUREG/CR-7240, Impact of Operating Parameters on Extended BWR Burnup Credit  + (NUREG/CR-7240, Impact of Operating Parameters on Extended BWR Burnup Credit)
• NUREG/CR-7244, Response of Nuclear Power Plant Instrumentation Cables Exposed to Fire Conditions  + (NUREG/CR-7244 Response of Nuclear Power Plant Instrumentation Cables Exposed to Fire Conditions)
• EPID:L-2019-JLD-0013  + (NUREG/CR-7245 State-of-the-Art Reactor Consequence Analyses (Soarca) Project Sequoyah Integrated Deterministic and Uncertainty Analyses)
• NUREG/CR-7245, State-of-the-Art Reactor Consequence Analyses (Soarca) Project  + (NUREG/CR-7245 State-of-the-Art Reactor Consequence Analyses (Soarca) Project)
• NUREG/CR-7246, Reliability Assessment of Remote Visual Examination  + (NUREG/CR-7246, Reliability Assessment of Remote Visual Examination)
• NUREG/CR-7249, Overview of Nuclear Data Uncertainty in Scale and Application to Light Water Reactor Uncertainty Analysis  + (NUREG/CR-7249, Overview of Nuclear Data Uncertainty in Scale and Application to Light Water Reactor Uncertainty Analysis)

• NUREG/CR-7250, Thermal-Hydraulic Experiments Using a Dry Cask Simulator  + (NUREG/CR-7250, Thermal-Hydraulic Experiments Using a Dry Cask Simulator)

• NUREG/CR-7251, Margins for Uncertainty in the Predicted Spent Fuel Isotopic Inventories for BWR Burnup Credit  + (NUREG/CR-7251 - Margins for Uncertainty in the Predicted Spent Fuel Isotopic Inventories for BWR Burnup Credit)
• NUREG/CR-7252, Validation of Keff Calculations for Extended BWR Burnup Credit  + (NUREG/CR-7252 Validation of Keff Calculations for Extended BWR Burnup Credit)
• NUREG/CR-7253, Technical Consideration for Seismic Isolation of Nuclear Facilities  + (NUREG/CR-7253, Technical Consideration for Seismic Isolation of Nuclear Facilities)
• ML19158A513  + (NUREG/CR-7254, Seismic Isolation of Nuclear Power Plants Using Sliding Bearings)
• NUREG/CR-7255, Seismic Isolation of Nuclear Power Plants Using Elastomeric Bearings  + (NUREG/CR-7255, Seismic Isolation of Nuclear Power Plants Using Elastomeric Bearings)
• ML20147A640  + (NUREG/CR-7256, Vol. 1, Effects of Environmental Conditions on Manual Actions for Flood Protection and Mitigation: Identifying Conditions, Characterizing Actions and Assessing Impacts)
• ML20147A665  + (NUREG/CR-7256, Vol. 2, Effects of Environmental Conditions on Manual Actions for Flood Protection and Mitigation: Review of the Research Literature)
• NUREG/CR-7257, Paleoliquefaction Studies in Moderate Seismicity Regions with a History of Large Events  + (NUREG/CR-7257, Paleoliquefaction Studies in Moderate Seismicity Regions with a History of Large Events)
• ML19192A128  + (NUREG/CR-7258 Technical Manual and Users Guide for Mildos Version 4.1)
• 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)