Spotlight
Publications Prepared by NRC Contractors
Documentation of technical, regulatory, or administrative information about NRC programs or activities prepared by a contractor. Other contractor reports may be available in ADAMS.
Document Identifier | Title |
|---|---|
Manual of Respiratory Protection Against Airborne Radioactive Material | |
Accidental Vapor Phase Explosions on Transportation Routes Near Nuclear Power Plants: Final Report January – April 1977 | |
Development and Verification of Fire Tests for Cable Systems and System Components: Quarterly Reports 2 and 3, September 1, 1977 – February 28, 1978 | |
SCALE Ver 4.4: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation | |
A Preliminary Report on Fire Protection Research Program Fire Barriers and Fire Retardant Coatings Tests | |
Nuclear Power Plant Fire Protection — Fire Barriers (Subsystems Study Task 3) | |
Nuclear Power Plant Fire Protection — Fire Detection (Subsystems Study Task 2) | |
A Preliminary Report on Fire Protection Research Program, Fire Barriers and Suppression (September 15, 1978 Test) | |
Nuclear Power Plant Fire Protection — Ventilation (Subsystems Study Task 1) | |
Nuclear Power Plant Fire Protection — Fire-Hazards Analysis (Subsystems Study Task 4) | |
Fire Protection Research Program Corner Effects Tests | |
A Radioactive Waste Disposal Classification System | |
Environmental Assessment of Ionization Chamber Smoke Detectors Containing Am-241 | |
Evaluation of Simulator Adequacy for the Radiation Qualification of Safety-Related Equipment | |
The NACOM Code for Analysis of Postulated Sodium Spray Fires in LMFBRs | |
Seismic Review Table | |
Investigation of Distorted-Geometry Simulation of Pool Dynamics in Horizontal-Vent BWR Containments | |
Development and Verification of Fire Tests for Cable Systems and System Components: Quarterly Report 12, March – May 1980 | |
Approaches to Acceptable Risk: A Critical Guide | |
A Characterization of Faults in the Appalachian Foldbelt | |
Electrical Insulators in a Reactor Accident Environment | |
Technology, Safety and Costs of Decommissioning Reference Nuclear Research and Test Reactors | |
Data Base for Radioactive Waste Management | |
Acceptance and Verification for Early Warning Fire Detection Systems: Interim Guide | |
Development and Testing of a Model for Fire Potential in Nuclear Power Plants | |
A Risk Comparison | |
Index of Risk Exposure and Risk Acceptance Criteria | |
Seismic Safety Margins Research Program Phase I Final Report | |
A Study of the Implications of Applying Quantitative Risk Criteria in the Licensing of Nuclear Power Plants in the United States | |
Fire Risk Analysis for Nuclear Power Plants | |
Technical Basis for Regulatory Guide 1.145, "Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants" | |
Probabilistic Models for the Behavior of Compartment Fires | |
PRA Procedures Guide: A Guide to the Performance of Probabilistic Risk Assessments for Nuclear Power Plants | |
Investigation of Fire Stop Test Parameters | |
Test and Criteria for Fire Protection of Cable Penetrations | |
Age-Specific Inhalation Radiation Dose Commitment Factors for Selected Radionuclides | |
Requirements for Establishing Detector Siting Criteria in Fires InvolvingElectrical Materials | |
Burn Mode Analysis of Horizontal Cable Tray Fires | |
Hydrogen Combustion Characteristics Related to Reactor Accidents | |
Final Results of the Hydrogen Igniter Experimental Program | |
Hazards to Nuclear Power Plants from Large Liquefied Natural Gas (LNG) Spills on Water | |
Fire Protection Research Program for the U.S. Nuclear Regulatory Commission: 1975–1981 | |
Allowable Shipment Frequencies for the Transport of Toxic Gases Near Nuclear Power Plants | |
Characteristics of Combustion Products: A Review of the Literature | |
Seismic Safety Margins Research Program: Equipment Fragility Data Base | |
Light Water Reactor Hydrogen Manual | |
Hydrogen Burn Survival: Preliminary Thermal Model and Test Results | |
Probabilistic Safety Analysis Procedures Guide | |
PAVAN: An Atmospheric-Dispersion Program for Evaluating Design-Basis Accidental Releases of Radioactive Materials from Nuclear Power Stations | |
Aging Effects on Fire-Retardant Additives in Organic Materials for Nuclear Plant Applications | |
Radioactive Effluents from Nuclear Power Plants | |
Nuclear Power Plant Electrical Cable Damageability Experiments | |
Regional Tectonics and Seismicity of Southwestern Iowa | |
User's Manual for FIRIN: A Computer Code to Estimate Accidental Fire and Airborne Releases in Nuclear Fuel Cycle Facilities | |
Potentially Damaging Failure Modes of High- and Medium-Voltage Electrical Equipment | |
Scenarios and Analytical Methods for UF6 Releases at NRC-Licensed Fuel Cycle Facilities | |
Investigation of Twenty-Foot Separation Distance as a Fire Protection Method as Specified in 10 CFR 50, Appendix R | |
COMPBRN — A Computer Code for Modeling Compartment Fires | |
The Los Alamos National Laboratory/New Mexico State University Filter Plugging Test Facility: Description and Preliminary Test Results | |
Status Report: Correlation of Electrical Cable Failure with Mechanical Degradation | |
Vulnerability of Nuclear Power Plant Structures to Large External Fires | |
A Methodology for Allocating Nuclear Power Plant Control Nuclear to Human or Automatic Control | |
Radiological Assessment: A Textbook on Environmental Dose Analyses | |
Measures of Risk Importance and Their Applications | |
Hydrogen:Air:Steam Flammability Limits and Combustion Characteristics in the FITS Vessel | |
A Review of the Limerick Generating Station Severe Accident Risk Assessment: Review of Core-Melt Frequency | |
Hydrogen-Burn Survival Experiments at Fully Instrumented Test Site (FITS) | |
Material Transport Analysis for Accident-Induced Flow in Nuclear Facilities | |
Response of Rubber Insulation Materials to Monoenergetic Electron Irradiations | |
The Effect of Thermal and Irradiation Aging Simulation Procedures on Polymer Properties | |
Hydrogen-Steam Jet-Flame Facility and Experiments | |
Evaluation of Suppression Methods for Electrical Cable Fires | |
Detonation Calculations Using a Modified Version of CSQII: Examples for Hydrogen-Air Mixtures | |
Accident-Induced Flow and Material Transport in Nuclear Facilities: A Literature Review | |
Engineering Characterization of Ground Motion: Task II: Summary Report | |
Survey and Evaluation of System Interaction Events and Sources | |
Extended Storage of Low-Level Radioactive Waste: Potential Problem Areas | |
Investigation of Cable and Cable System Fire Test Parameters | |
Data Analyses for Nevada Test Site (NTS) Premixed Combustion Tests | |
Evaluation of Current Methodology Employed in Probabilistic Risk Assessment (PRA) of Fire Events at Nuclear Power Plants | |
Probability-Based Evaluation of Selected Fire Protection Features in Nuclear Power Plants | |
Evaluation of Available Data for Probabilistic Risk Assessments (PRA) of Fire Events at Nuclear Power Plants | |
Mitigative Techniques for Ground-Water Contamination Associated With Severe Nuclear Accidents | |
Investigation of High-Efficiency Particulate Air Filter Plugging by Combustion Aerosols | |
Investigation of Potential Fire-Related Damage to Safety-Related Equipment in Nuclear Power Plants | |
Full-Scale Measurements of Smoke Transport and Deposition in Ventilation System Ductwork | |
Review of Light Water Reactor Regulatory Requirements | |
Update of Part 61 – Impacts Analysis Methodology: Codes and Example Problems | |
Comparison of Dynamic Characteristics of Fukushima Nuclear Power Plant Containment Building Determined From Tests and Earthquakes | |
Tornado Climatology of the Contiguous United States | |
The Use of a Field Model To Assess Fire Behavior in Complex Nuclear Power Plant Enclosures: Present Capabilities and Future Prospects | |
Recommendations To The Nuclear Regulatory Commission On Trial Guidelines For Seismic Margin Reviews Of Nuclear Power Plants — Draft Report for Comment | |
Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems | |
Design Features for Enhancing International Safeguards of Away-from- Reactor Dry Storage for Spent LWR Fuel | |
An Experimental Investigation of Internally Ignited Fires in Nuclear Power Plant Control Cabinets | |
Analysis of Diffusion Flame Tests | |
FIRAC User's Manual: A Computer Code to Simulate Fire Accidents in Nuclear Facilities | |
COMPBRN III - A Computer Code for Modeling Compartment Fires | |
Description and Testing of an Apparatus for Electrically Initiating Fires Through Simulation of a Faulty Connection | |
Users' Guide for a Personal-Computer-Based Nuclear Power Plant Fire Data Base | |
Screening Tests of Representative Nuclear Power Plant Components Exposed to Secondary Environments Created by Fires | |
Transient Fire Environment Cable Damageability Test Results | |
Geochemical Studies of Commercial Low-Level Radioactive Waste Disposal Sites | |
Environmentally Assisted Cracking in Light Water Reactors: Annual Report | |
Precursors to Potential Severe Core Damage Accidents: 1998 A Status Report | |
Quantitative Data on the Fire Behavior of Combustible Materials Found in Nuclear Power Plants: A Literature Review | |
Heat and Mass Release for Some Transient Fuel Source Fires: A Test Report | |
Enclosure Environment Characterization Testing for the Base Line Validation of Computer Fire Simulation Codes | |
Combustion Aerosols Formed During Burning of Radioactively Contaminated Materials, Experimental Results | |
Guide for Preparing Operating Procedures for Shipping Packages | |
Seismic Margin Review of the Maine Yankee Atomic Power Station | |
Shipping Container Response to Severe Highway and Railway Accident Conditions | |
MELCOR Validation and Verification: 1986 Papers | |
Methods for External Event Screening Quantification: Risk Methods Integration and Evaluation Program (RMIEP) Methods Development | |
Procedures for the External Event Core Damage Frequency Analyses for NUREG-1150 | |
Development and Application of a Computer Model for Large-Scale Flame Acceleration Experiments | |
Interpretation of Bioassay Measurements | |
Detonability of H2-Air-Diluent Mixtures | |
Fire Environment Determination in the LaSalle Nuclear Power Plant Control Rroom | |
An Approach to the Quantification of Seismic Margins in Nuclear Power Plants: The Importance of BWR Plant Systems and Functions to Seismic Margins | |
Experimental Results Pertaining to the Performance of Thermal Igniters | |
Tactical Exercise Planning Handbook | |
Steam Generator Tube Integrity Program/Steam Generator Group Project: Final Project Summary Report | |
Tactical Training Reference Manual | |
Seismic Failure and Cask Drop Analyses of the Spent Fuel Pools at Two Representative Nuclear Power Plants | |
A Computer Code for Fire Protection and Risk Analysis of Nuclear Plants | |
Individual Plant Examinations for External Events: Review Plan and Evaluation Criteria | |
FLAME Facility: The Effect of Obstacles and Transverse Venting on Flame Acceleration and Transition to Detonation for Hydrogen-Air Mixtures at Large Scale | |
Sulfate-Attack Resistance and Gamma-Irradiation Resistance of Some Portland Cement Based Mortars | |
Value/Impact Analyses of Accident Preventive and Mitigative Options for Spent Fuel Pools | |
Recommendations for Resolution of Public Comments on USI A-40, “Seismic Design Criteria” | |
A Summary of Nuclear Power Plant Fire Safety Research at Sandia National Laboratories, 1975–1987 | |
Initial Assessment of the Mechanisms and Significance of Low-Temperature Embrittlement of Cast Stainless Steels in LWR Systems | |
Elements of an Approach to Performance-Based Regulatory Oversight | |
Anchor Bolt Behavior and Strength During Earthquakes | |
A Review of the Three Mile Island-1 Probabilistic Risk Assessment | |
Service Life of Concrete | |
Reliability Study | |
Residual Radioactive Contamination From Decommissioning: User's Manual DandD Version 2.1 | |
Hydrogen-Air-Diluent Detonation Study for Nuclear Reactor Safety Analyses | |
A Performance Assessment Methodology for Low-Level Waste Facilities | |
Models for Estimation of Service Life of Concrete Barriers in Low-Level Radioactive Waste Disposal | |
An Investigation of the Effects of Thermal Aging on the Fire Damageability of Electric Cables | |
Dating and Earthquakes: Review of Quaternary Geochronology and Its Application to Paleoseismology | |
Evaluation of Generic Issue 57 | |
The High Level Vibration Test Program – Final Report | |
Heavy-Section Steel Irradiation Program: Progress Report April 1997 - March 1998 | |
Electromagnetic Compatibility Testing for Conducted Susceptibility Along Interconnecting Signal Lines | |
The Impact of Thermal Aging on the Flammability of Electric Cables | |
Incorporating Aging Effects into Probabilistic Risk Assessment — A Feasibility Study Utilizing Reliability Physics Models | |
Submergence and High Temperature Steam Testing of Class lE Electrical Cables | |
Evaluation of Exposure Limits to Toxic Gases for Nuclear Reactor Control Room Operators | |
Design, Instrumentation and Testing of a Steel Containment Vessel Model | |
Results of Field Studies at the Maricopa Environmental Monitoring Site, Arizona | |
Comparing Monitoring Strategies at the Maricopa Environmental Monitoring Site, Arizona | |
Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels | |
Iodine Chemical Forms in LWR Severe Accidents | |
Re-evaluation of Regulatory Guidance Provided in Regulatory Guides 1.142 and 1.143 | |
Recommendations to the NRC on Acceptable Standard Format and Content for the Fundamental Nuclear Material Control (FNMC) Plan Requiredfor Low-Enriched Uranium Enrichment Facilities | |
Evaluation of WF-70 Weld Metal From the Midland Unit 1 Reactor Vessel | |
Hydrogeologic Performance Assessment of the Commercial Low-Level Radioactive Waste Disposal Facility Near West Valley, New York | |
Field Investigations for Foundations of Nuclear Power Facilities | |
Laboratory Investigations of Soils and Rocks For Engineering Analysis and Design of Nuclear Power Facilities | |
Technical Bases for Regulatory Guide for Soil Liquefaction | |
Risk Evaluation for a Westinghouse PWR, Effects of Fire Protection System Actuation on Safety-Related Equipment: Evaluation of Generic Issue 57 | |
Risk Evaluation for a B&W Pressurized Water Reactor, Effects of Fire Protection System Actuation on Safety-Related Equipment: Evaluation of Generic Issue 57 | |
Risk Evaluation for a General Electric BWR, Effects of Fire Protection System Actuation on Safety-Related Equipment: Evaluation of Generic Issue 57 | |
Advanced Human-system Interface Design Review Guideline | |
Review of the Technical Basis and Verification of Current Analysis Methods Used to Predict Seismic Response of Spent Fuel Storage Racks | |
Evaluation of a Performance Assessment Methodology for Low-Level Radioactive Waste Disposal Facilities: Evaluation of Modeling Approaches | |
Technical Basis for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related I&C Systems | |
A Simplified Model of Aerosol Removal by Containment Sprays | |
Fire Modeling of the Heiss Dampf Reaktor Containment | |
Perspectives on Reactor Safety | |
Analysis of Crack Initiation and Growth in the High Level Vibration Test at Tadotsu | |
Data Communications | |
Reviewing Real-Time Performance of Nuclear Reactor Safety Systems | |
The Programmable Logic Controller and Its Application in Nuclear Reactor Systems | |
An Analysis of Operational Experience During Low Power and Shutdown and a Plan for Addressing Human Reliability Assessment Issues | |
Aging, Loss-of-Coolant Accident (LOCA), and High Potential Testing of Damaged Cables | |
Software Reliability and Safety in Nuclear Reactor Protection Systems | |
PWR and BWR Pressure Vessel Fluence Calculation Benchmark Problems and Solutions | |
MELCOR Computer Code Manuals | |
Tensile-Property Characterization of Thermally Aged Cast Stainless Steels | |
SCDAP/RELAP5/MOD 3.3 Code Manual | |
A Summary of the Fire Testing Program at the German HDR Test Facility | |
Revised Analyses of Decommissioning for the Reference Boiling Water Reactor Power Station | |
A Simplified Model of Aerosol Removal by Natural Processes in Reactor Containments | |
An Empirical Investigation of Operator Performance in Cognitively Demanding Simulated Emergencies | |
Computer Codes for Evaluation of Control Room Habitability (HABIT) | |
Value of Public Health and Safety Actions and Radiation Dose Avoided | |
High-Temperature Hydrogen-Air- Steam Detonation Experiments in the BNL Small-Scale Development Apparatus | |
Production and Testing of the Revised VITAMIN-B6 Fine-Group and the BUGLE-93 Broad-Group Neutron/Photon Cross-Section Libraries Derived From END/B-VI.3 Nuclear Data | |
An Assessment of Fire Vulnerability for Aged Electrical Relays | |
Radioanalytical Technology for 10 CFR Part 61 and Other Selected Radionuclides: Literature Review | |
Technical Guidelines for Aseismic Design of Nuclear Power Plants | |
Multidisciplinary Framework for Human Reliability Analysis with an Application to Errors of Commission and Dependency | |
Common-Cause Failure Database and Analysis System: Event Data Collection, Classification, and Coding | |
Mechanical Properties of Thermally Aged Cast Stainless Steels from Shippingport Reactor Components | |
Method for Performing Diversity and Defense-in-Depth Analyses of Reactor Protection Systems | |
Quality Assurance Inspections for Shipping and Storage Containers | |
Atmospheric Relative Concentrations in Building Wakes | |
Fracture Toughness Testing With Cracked Round Bars: Feasibility Study | |
Radiation Dose Estimates for Radiopharmaceuticals | |
Hydrologic Evaluation Methodology for Estimating Water Movement Through the Unsaturated Zone at Commercial Low-Level Radioactive Waste Disposal Sites | |
A Technique for Human Error Analysis (ATHEANA) | |
Assessment of United States Industry Structural Codes and Standards for Application to Advanced Nuclear Power Reactors | |
Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages | |
Drywell Debris Transport Study | |
Recommendations for Probabilistic Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts | |
Effects of Radionuclide Concentrations by Cement/Ground-Water Interactions in Support of Performance Assessment of Low-Level Radioactive Waste Disposal Facilities | |
Literature Review of Environmental Qualification of Safety-Related Electric Cables | |
Integrated System Validation: Methodology and Review Criteria | |
Human Factors Engineering (HFE) Insights for Advanced Reactors Based Upon Operating Experience | |
Environmental Testing of an Experimental Digital Safety Channel | |
Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety | |
Nuclear Fuel Cycle Facility Accident Analysis Handbook | |
Self-Monitoring Surveillance System for Prestressing Tendons | |
A Proposed Acceptance Process for Commercial Off-the-Shelf (COTS) Software in Reactor Applications | |
Report on Aging of Nuclear Power Plant Reinforced Concrete Structures | |
Assessment of the DCH Issue for Plants with Ice Condenser Containments | |
Effects of Thermal Aging on Fracture Toughness and Charpy-Impact Strength of Stainless Steel Pipe Welds | |
Recommended Electromagnetic Operating Envelopes for Safety-Related I&C Systems in Nuclear Power Plants | |
Analysis of Spent Fuel Heatup Following Loss of Water in a Spent Fuel Pool | |
Review Guidelines on Software Languages for Use in Nuclear Power Plant Safety Systems | |
Characterization of Flaws in U.S. Reactor Pressure Vessels | |
Circuit Bridging of Components by Smoke | |
Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities | |
Motor-Operated Valve (MOV) Actuator Motor and Gearbox Testing | |
Technical Basis for Environmental Qualification of Microprocessor-Based Safety-Related Equipment in Nuclear Power Plants | |
Owners of Nuclear Power Plants | |
The Effect of Initial Temperature on Flame Acceleration and Deflagration-to-Detonation Transition Phenomenon | |
Steam Generator Tube Integrity Program Annual Report | |
The Effect of Lateral Venting on Deflagration-to-Detonation Transition in Hydrogen-Air-Steam Mixtures at Various Initial Temperatures | |
SecPop: Sector Population, Land Fraction, and Economic Estimation Program | |
Deliberate Ignition of Hydrogen-Air-Steam Mixtures in Condensing Steam Environments | |
FRAPCON-3 Updates, Including Mixed-Oxide Fuel Properties | |
Effects of Smoke on Functional Circuits | |
A Methodology for Analyzing Precursors to Earthquake-Initiated and Fire-Initiated Accident Sequences | |
Finite Element Analyses for Seismic Shear Wall International Standard Problem | |
Large-Scale Vibration Tests of Main Steam and Feedwater Piping Systems With Conventional and Energy-Absorbing Supports | |
Uncertainty Analyses of Infiltration and Subsurface Flow and Transport for SDMP Sites | |
Low-Level Radioactive Waste Classification, Characterization, and Assessment: Waste Streams and Neutron-Activated Metals | |
Kalinin VVER-1000 Nuclear Power Station Unit 1 PRA: Procedure Guides for a Probabilistic Risk Assessment (English Version) | |
U.S. Nuclear Power Plant Operating Cost and Experience Summaries | |
Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels | |
Evaluation of the Hualien Quarter Scale Model Seismic Experiment | |
The Effects of Surface Condition on an Ultrasonic Inspection: Engineering Studies Using Validated Computer Model | |
An Approach for Estimating the Frequencies of Various Containment Failure Modes and Bypass Events | |
Results and Insights on the Impact of Smoke on Digital Instrumentation and Control | |
Guidance for Performing Probabilistic Seismic Hazard Analysis for a Nuclear Plant Site: Example Application to the Southeastern United States | |
Comparison of Irradiation-Induced Shifts of KJc and Charpy Impact Toughness for Reactor Pressure Vessel Steels | |
Testing of dc-Powered Actuators for Motor-Operated Valves | |
Probabilistic Liquefaction Analysis | |
Vapor Explosions in a One-Dimensional Large Scale Geometry with Simulant Melts | |
Recommendations for Revision of Regulatory Guide 1.78 | |
Automated Seismic Event Monitoring System | |
The Role of Organic Complexants and Colloids in the Transport of Radionuclides by Groundwater | |
The Effects of Aging at 343°C on the Microstructure and Mechanical Properties of Type 308 Stainless Steel Weldments | |
Atom Probe Tomography Characterization of the Solute Distributions in a Neutron-Irradiated and Annealed Pressure Vessel Steel Weld | |
Solubility and Leaching of Radionuclides in Site Decommissioning Management Plan (SDMP) Slags | |
Advanced Information Systems Design: Technical Basis and Human Factors Review Guidance | |
Computer-Based Procedure Systems: Technical Basis and Human Factors Review Guidance | |
Soft Controls: Technical Basis and Human Factors Review Guidance | |
Maintainability of Digital Systems: Technical Basis and Human Factors Review Guidance | |
Human Systems Interface and Plant Modernization Process: Technical Basis and Human Factors Review Guidance | |
Advanced NDE for Steam Generator Tubing | |
Reevaluation of Regulatory Guidance on Modal Response Combination Methods for Seismic Response Spectrum Analysis | |
Adsorption and Desorption Behavior of Selected 10 CFR Part 61 Radionuclides From Ion Exchange Resin by Waters of Different Chemical Composition | |
Environmental Assessment: San Bernadino National Wildlife Refuge Well 10 | |
PUFF-III: A Code for Processing ENDF Uncertainty Data Into Multigroup Covariance Matrices | |
International Comparative Assessment Study of Pressurized Thermal Shock in Reactor Pressure Vessels | |
Comparison of Estimated Ground-Water Recharge Using Different Temporal Scales of Field Data | |
A Study of Air-Operated Valves in U.S. Nuclear Power Plants | |
Sensitivity and Uncertainty Analyses Applied to Criticality Safety Validation | |
Information on Hydrologic Conceptual Models, Parameters, Uncertainty Analysis, and Data Sources for Dose Assessments at Decommissioning Sites | |
TRAC-M Programmer's Guide: Fortran 77 Version 5.5 | |
KENO3D Visualization Tool for KENO V.a and KENO-VI Geometry Models | |
Pressure and Leak-Rate Tests and Models for Predicting Failure of Flawed Steam Generator Tubes | |
Survey of Waste Solidification Process Technologies | |
Standard Review Plan for Training and Qualifications Plans for Security Personnel at Category I Fuel Facilities | |
Evaluation of Terminated Licenses Parts 30, 40, and 70: The Terminated License Tracking System | |
Reexamination of Spent Fuel Shipment Risk Estimates | |
Hydrogen Generation in TRU Waste Transportation Packages | |
Interaction of Zinc Vapor with Zircaloy and the Effect of Zinc Vapor on the Mechanical Properties of Zircaloy | |
Probabilistic Dose Analysis Using Parameter Distributions Developed For RESRAD and RESRAD-BUILD Codes | |
Evaluation Of Risk Associated With Intergranular Stress Corrosion Cracking In Boiling Water Reactor Internals | |
Pretest Round Robin Analysis of a Prestressed Concrete Containment Vessel Model | |
Assessment of Age-Related Degradation of Structures and Passive Components for U.S. Nuclear Power Plants | |
Review Templates for Computer-Based Reactor Protection Systems | |
Ampacity Derating and Cable Functionality for Raceway Fire Barriers | |
Summary and Categorization of Public Comments on Controlling the Disposition of Solid Materials | |
A Critical Review of the Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel Pool Storage | |
Advanced Alarm Systems: Revision of Guidance and Its Technical Basis | |
Pretest Analysis of a 1:4-Scale Prestressed Concrete Containment Vessel Model | |
Experience With the Scale Criticality Safety Cross-Section Libraries | |
Irradiation-Assisted Stress Corrosion Cracking of Model Austenitic Stainless Steel Alloys | |
Testing, Verifying, and Validating SAPHIRE Versions 6.0 and 7.0 | |
Proposed Approach for Reviewing Changes to Risk-Important Human Actions | |
The Effects of Interface Management Tasks on Crew Performance and Safety in Complex, Computer-Based Systems: Overview and Main Findings | |
The Effects of Alarm Display, Processing, and Availability on Crew Performance | |
Probabilistic Modules for the RESRAD and RESRAD-BUILD Computer Codes: User Guide | |
POLIDENT: A Module for Generating Continuous-Energy Cross Sections From ENDF Resonance Data | |
Hydrologic Uncertainty Assessment for Decommissioning Sites: Hypothetical Test Case Applications | |
LAPUR 5.2 Verification and User's Manual | |
Development of Probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0 Computer Codes | |
A Review of Large-Scale Fracture Experiments Relevant to Pressure Vessel Integrity Under Pressurized Thermal Shock Conditions | |
Nuclide Importance to Criticality Safety, Decay Heating, and Source Terms Related to Transport and Interim Storage of High-Burnup LWR Fuel | |
Review of Technical Issues Related to Predicting Isotopic Compositions and Source Terms for High-Burnup LWR Fuel | |
Limited Burnup Credit in Criticality Safety Analysis: A Comparison of ISG-8 and Current International Practice | |
Environmental Effects of Extending Fuel Burnup Above 60 Gwd/MTU | |
Assessment of Environmental Qualification Practices and Condition Monitoring Techniques for Low-Voltage Electric Cables | |
Historical Case Analysis of Uranium Plume Attenuation | |
Capacity of Steel & Concrete Containment Vessels with Corrosion Damage | |
Seismic Analysis of a Reinforced Concrete Containment Vessel Model | |
Surface Complexation Modeling of Uranium (VI) Adsorption on Natural Mineral Assemblages | |
Extending the Dynamic Flowgraph Methodology (DFM) to Model Human Performance and Team Effects | |
Environmental Assessment of Major Revision of 10 CFR Part 71 | |
Summary and Categorization of Public Comments on the Major Revision of 10 CFR Part 71 | |
Regulatory Analysis of Major Revision of 10 CFR Part 71 | |
Hanford Tank Waste Remediation System Pretreatment Chemistry and Technology | |
Probability-Based Evaluation of Degraded Reinforced Concrete Components in Nuclear Power Plants | |
Recommendations on Fuel Parameters for Standard Technical Specifications for Spent Fuel Storage Casks | |
Environmental Effects on Fatigue Crack Initiation in Piping and Pressure Vessel Steels | |
OPUS/PlotOPUS: An ORIGEN-S Post-Processing Utility and Plotting Program for SCALE | |
Assessment of the Relevance of Displacement Bases Design Methods/Criteria to Nuclear Plant Structures | |
TRAC-M Validation Test Matrix | |
Effects of Alloy Chemistry, Cold Work, and Water Chemistry on Corrosion Fatigue and Stress Corrosion Cracking of Nickel Alloys and Welds | |
TRAC-M/FORTRAN 90 (Version 3.0) User's Manual | |
TRAC-M/FORTRAN 90 (Version 3.0) Theory Manual | |
TRAC-M/FORTRAN 90 (Version 3.0) Programmer's Manual | |
Aging Management and Performance of Stainless Steel Bellows in Nuclear Power Plants | |
Technical Basis for Revision of Regulatory Guidance on Design Ground Motions: Hazard- and Risk-consistent Ground Motion Spectra Guidelines | |
Field Studies for Estimating Uncertainties in Ground-Water Recharge Using Near-Continuous Peizometer Data | |
TRAC-M/F77, Version 5.5 Developmental Assessment Manual | |
Zinc-Zircaloy Interaction in Dry Storage Casks | |
A Baseline Risk-Informed, Performance-Based Approach for In Situ Leach Uranium Extraction Licensees | |
Digital Systems Software Requirements Guidelines | |
Effects of Deregulation on Safety: Implications Drawn From The Aviation, Rail and United Kingdom Nuclear Power Industries | |
Bases for Predicting the Earliest Penetrations Due to SCC for Alloy 600 on the Secondary Side of PWR Steam Generators | |
Risk Methods Insights Gained from Fire Incidents | |
FRAPTRAN: NRC's Computer Code | |
Application of Microprocessor-Based Equipment in Nuclear Power Plants-Technical Basis for a Qualification Methodology | |
Phenomenon Identification and Ranking Tables (PIRTs) for Rod Ejection Accidents in Pressurized Water Reactors Containing High Burnup Fuel | |
Phenomenon Identification and Ranking Tables (PIRTs) for Power Oscillations Without Scram in Boiling Water Reactors Containing High Burnup Fuel | |
Phenomenon Identification and Ranking Tables (PIRTs) for Loss-of-Coolant Accidents in Pressurized and Boiling Water Reactors Containing High Burnup Fuel | |
Dry Cask Storage Characterization Project - Phase 1: CASTOR V/21 Cask Opening and Examination | |
Advanced Nondestructive Evaluation for Steam Generator Tubing | |
Computational Benchmark for Estimation of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit | |
STARBUCS: A Prototypic SCALE Control Module for Automated Criticality Safety Analyses Using Burnup Credit | |
Integrating Digital and Conventional Human-System Interfaces: Lessons Learned from a Control Room Modernization Program | |
Performance of MOV Stem Lubricants at Elevated Temperature | |
The Human Performance Evaluation Process: A Resource for Reviewing the Identification and Resolution of Human Performance Problems | |
A Comparative Analysis of Special Treatment Requirements for Systems, Structures, and Components (SSCs) of Nuclear Power Plants With Commercial Requirements of Non-Nuclear Power Plants | |
Review of Findings for Human Performance Contribution to Risk in Operating Events | |
Review of Industry Responses to NRC Generic Letter 97-06 on Degradation of Steam Generator Internals | |
Technical Basis for Calculating Radiation Doses for the Building Occupancy Scenario Using the Probabilistic RESRAD-BUILD 3.0 Code | |
Analysis of Potential for Jet-Impingement Erosion from Leaking Steam Generator Tubes During Severe Accidents | |
Large-Scale Molecular Dynamics Simulations of Metal Sorption onto the Basal Surfaces of Clay Minerals | |
Radionuclide-Chelating Agent Complexes in Low-Level Radioactive Decontamination Waste: Stability, Adsorbtion, and Transport Potential | |
Parametric Study of Effect of Control Rods for PWR Burnup Credit | |
Study of the Effect of Integral Burnable Absorbers for PWR Burnup Credit | |
Parametric Study of the Effect of Burnable Poison Rods for PWR Burnup Credit | |
Generic-Safety-Issue (GSI) 191 Technical Assessment | |
Aging Assessment of Safety-Related Fuses Used in Low- and Medium- Voltage Applications in Nuclear Power Plants | |
Burnup Credit PIRT Report | |
Development of Technical Basis for Leak-Before-Break Evaluation Procedures | |
Release of Radionuclides and Chelating Agents from Full-System Decontamination Ion-Exchange Resins | |
Evaluation of Hydrologic Uncertainty Assessments for Decommissioning Sites Using Complex and Simplified Models | |
Spent Nuclear Fuel Transportation Package Performance Study Issues Report | |
Technical Basis for Revision of Regulatory Guidance on Design Ground Motions: Development of Hazard- & Risk-Consistent Seismic Spectra for Two Sites | |
GSI-191: Thermal-Hydraulic Response of PWR Reactor Coolant System & Containments to Selected Accident Sequences | |
GSI-191: The Impact of Debris Induced Loss of ECCS Recirculation on PWR Core Damage Frequency | |
GSI-191: Separate-Effects Characterization of Debris Transport in Water | |
GSI-191: Integrated Debris-Transport Tests in Water Using Simulated Containment Floor Geometries | |
Validation on Failure & Leak-Rate Correlations for Stress Corrosion Cracks in Steam Generator Tubes | |
Human Performance Characterization in the Reactor Oversight Process | |
Cable Insulation Resistance Measurements Made During Cable Fire Tests | |
Results and Analysis of The ASTM Round Robin On Reconstitution | |
The Effects of Composition and Heat Treatment on Hardening and Embrittlement of Reactor Pressure Vessel Steels | |
Effects of Adsorption Constant Uncertainty on Containment Plume Migration: One- and Two-Dimensional Numerical Studies | |
Recommendations on the Credit for Cooling Time in PWR Burnup Credit Analyses | |
Comparison of U.S. Military and International Electromagnetic Compatibility Guidance | |
Structural Seismic Fragility Analysis of the Surry Containment | |
Use of Computerized Microtomography to Examine the Relationships of Sorption Sites in Alluvial Soils to Iron and Pore Space Distributions | |
Evaluation of Eddy Current Reliability from Steam Generator Mock-Up Round-Robin | |
ANL/CANTIA: A Computer Code for Steam Generator Integrity Assessments | |
Mechanism and Estimation of Fatigue Crack Initiation in Austenitic Stainless Steels in LWR Environments | |
Evaluation of Aging and Qualification Practices for Cable Splices Used in Nuclear Plants | |
Results From Pressure and Leak-Rate Testing of Laboratory-Degraded Steam Generator Tubing | |
Eddy Current Reliability Results from the Steam Generator Mock-up Analysis Round-Robin: Revision 1 | |
Behavior of PWR Reactor Coolant System Components, Other than Steam Generator Tubes, Under Severe Accident Conditions | |
Numerical Simulation of the Howard Street Tunnel Fire, Baltimore, Maryland, July 2001 | |
Evaluation of Aging and Environmental Qualification Practices for Power Cables Used in Nuclear Power Plants | |
A Comparison of Three Round Robin Studies on ISI Reliability of Wrought Stainless Steel Piping | |
Isotopic Analysis of High-Burnup PWR Spent Fuel Samples From the Takahama-3 Reactor | |
Analysis of Rail Car Components Exposed to a Tunnel Fire Environment | |
Assessment of Reactivity Margins and Loading Curves for PWR Burnup-Credit Cask Designs | |
Recommendations for Addressing Axial Burnup in PWR Burnup Credit Analyses | |
Recommendations for Shielding Evaluations for Transport & Storage Packages | |
Second U.S. Nuclear Regulatory Commission International Steam Generator Tube Integrity Research Program | |
A Comprehensive Strategy of Hydrogeologic Modeling and Uncertainty Analysis for Nuclear Facilities and Sites | |
MOV Stem Lubricant Aging Research | |
Results of NRC-Sponsored Stellite 6 Aging & Friction Testing | |
Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance | |
Posttest Analysis of the NUPEC/NRC 1:4 Scale Prestressed Concrete Containment Vessel Model | |
Overpressurization Test of a 1:4-Scale Prestressed Concrete Containment Vessel Model | |
Strategies for Application of Isotopic Uncertainties in Burnup Credit | |
Emerging Technologies in Instrumentation and Controls | |
Issues and Recommendations for Advancement of PRA Technology In Risk-Informed Decision Making | |
Final Report on Advanced Nondestructive Evaluation for Steam Generator Tubing for the Second International Steam Generator Tube Integrity Program | |
Review of the Margins for ASME Code Fatigue Design Curve: Effects of Surface Roughness and Material Variability | |
Review and Assessment of Codes and Procedures for HTGR Components | |
A Generalized Procedure for Generating Flaw-Related Inputs for the FAVOR Code | |
Drop Test Results for the Combustion Engineering Model No. ABB-2901 Fuel Pellet Shipping Package | |
Common-Cause Failure Event Insights | |
Application of Surface Complexation Modeling to Describe Uranium (VI) Adsorption and Retardation at the Uranium Mill Tailings Site at Naturita, Colorado | |
Solubility and Leaching of Radionuclides in Site Decommissioning Management Plan (SDMP) Soil and Ponded Wastes | |
Collaborative Study of NUPEC Seismic Field Test Data for NPP Structures | |
Handbook of Parameter Estimation for Probabilistic Risk Assessment | |
Materials Behavior in HTGR Environments | |
Literature Review and Assessment of Plant and Animal Transfer Factors Used in Performance Assessment Modeling | |
Fracture Toughness and Crack Growth Rates of Irradiated Austenitic Stainless Steels | |
Assessment of Internal Oxidation (IO) as a Mechanism for Submodes of Stress Corrosion Cracking (SCC) that Occur on the Secondary Side of Steam Generators | |
Examination of Spent PWR Fuel Rods After 15 Years in Dry Storage | |
Regulatory Effectiveness of Unresolved Safety Issue (USI) A-45, "Shutdown Decay Heat Removal Requirements" | |
Formal Methods of Decision Analysis Applied to Prioritization of Research and Other Topics | |
Circuit Analysis: Failure Mode and Likelihood Analysis | |
Effects of Fuel Failure on Criticality Safety and Radiation Dose for Spent Fuel Casks | |
Comparing Ground-Water Recharge Estimates Using Advanced Monitoring Techniques and Models | |
The Battelle Integrity of Nuclear Piping (BINP) Program Final Report | |
Technical Basis for Regulatory Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing Requirements Specified in 10 CFR 50.54(m) | |
Fort Saint Vrain Gas Cooled Reactor Operational Experience | |
The Technical Basis for the NRC's Guidelines for External Risk Communication | |
A Risk-Informed Basis for Establishing Non-Fixed Surface Contamination Limits for Spent Fuel Transportation Casks | |
Advanced Reactor Licensing: Experience with Digital I&C Technology in Evolutionary Plants | |
Combined Estimation of Hydrogeologic Conceptual Model and Parameter Uncertainty | |
TRISO-Coated Particle Fuel Phenomenon Identification and Ranking Tables (PIRTs) for Fission Product Transport Due to Manufacturing, Operations, and Accidents | |
Sensitivity Analysis Applied to the Validation of the 10B Capture Reaction in Nuclear Fuel Casks | |
Air Oxidation Kinetics for Zr-Based Alloys | |
Preliminary Validation of a Methodology for Assessing Software Quality | |
Analysis of In-Vessel Retention and Ex-Vessel Fuel Coolant Interaction for AP1000 | |
EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities | |
Hydrogen Effects on Air Oxidation of Zirlo Alloy | |
Comparison of Average Transport and Dispersion Among a Gaussian, a Two-Dimensional, and a Three-Dimensional Model | |
Fracture Analysis of Vessels — Oak Ridge FAVOR v04.1, Computer Code: Theory and Implementation of Algorithms, Methods, and Correlations | |
Fracture Analysis of Vessels — Oak Ridge FAVOR, V04.1, Computer Code: User’s Guide | |
RELAP5/MOD3.2.2 Gamma Assessment for Pressurized Thermal Shock Applications | |
PRA Procedures and Uncertainty for PTS Analysis | |
An Assessment of Visual Testing | |
Barrier Integrity Research Program | |
Development of Evacuation Time Estimate Studies for Nuclear Power Plants | |
Identification and Analysis of Factors Affecting Emergency Evacuations | |
Parametric Evaluation of Seismic Behavior of Freestanding Spent Fuel Dry Cask Storage Systems | |
Technical Basis for Regulatory Guidance on Lightning Protection in Nuclear Power Plants | |
Small-Scale Experiments: Effects of Chemical Reactions on Debris-Bed Head Loss — A Subtask of GSI-191 | |
A Reliability Physics Model for Aging of Cable Insulation Materials | |
Consideration of Geochemical Issues in Groundwater Restoration at Uranium In-Situ Leach Mining Facilities | |
Documentation and Applications of the Reactive Geochemical Transport Model RATEQ | |
Corrosion Rate Measurements and Chemical Speciation of Corrosion Products Using Thermodynamic Modeling of Debris Components to Support GSI-191 | |
GSI-191: Experimental Studies of Loss-of-Coolant-Accident-Generated Debris Accumulation and Head Loss with Emphasis on the Effects of Calcium Silicate Insulation | |
Boric Acid Corrosion of Light Water Reactor Pressure Vessel Materials | |
Risk-Informed Assessment of Degraded Buried Piping Systems in Nuclear Power Plants | |
Characterization and Head-Loss Testing of Latent Debris from Pressurized-Water-Reactor Containment Buildings | |
Effect of Material Heat Treatment on Fatigue Crack Initiation in Austenitic Stainless Steels in LWR Environments | |
Steam Generator Tube Integrity Issues: Pressurization Rate Effects, Failure Maps, Leak Rate Correlation Models, and Leak Rates in Restricted Areas | |
Argonne Model Boiler Facility: Topical Report | |
Soil and Groundwater Sample Characterization and Agricultural Practices for Assessing Food Chain Pathways in Biosphere Models | |
Assessment of Wireless Technologies and Their Application at Nuclear Facilities | |
The SPAR-H Human Reliability Analysis Method | |
Model Abstraction Techniques for Soil-Water Flow and Transport | |
Screen Penetration Test Report | |
Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire Scenario | |
DORT/TORT Analysis of the Hatch Unit-1 Jet Pump Riser Brace Pad Neutron Dosimetry Measurements with Comparisons to Predictions Made with RAMA | |
Emerging Technologies in Instrumentation and Controls: An Update | |
Seismic Analysis of Simplified Piping Systems for the NUPEC Ultimate Strength Piping Test Program | |
Reevaluation of Station Blackout Risk at Nuclear Power Plants | |
Crack Growth Rates of Irradiated Austenitic Stainless Steel Weld Heat Affected Zone in BWR Environments | |
Irradiation-Assisted Stress Corrosion Cracking Behavior of Austenitic Stainless Steels Applicable to LWR Core Internals | |
Modeling Adsorption Processes: Issues in Uncertainty, Scaling, and Prediction | |
Spent Fuel Transportation Package Response to the Caldecott Tunnel Fire Scenario | |
Technical Review of On-Line Monitoring Techniques for Performance Assessment | |
Assessment of Seismic Analysis Methodologies for Deeply Embedded Nuclear Power Plant Structures | |
Assessment of Void Swelling in Austenitic Stainless Steel Core Internals | |
A Combined Analytical Study to Characterize Uranium Soil and Sediment Contamination: The Case of the Naturita UMTRA Site and the Role of Grain Coatings | |
The Effect of Elevated Temperature on Concrete Materials and Structures — A Literature Review | |
Current State of Reliability Modeling Methodologies for Digital Systems and Their Acceptance Criteria for Nuclear Power Plant Assessments | |
Effects of Insulation Debris on Throttle-Valve Flow Performance: A Subtask of GSI-191 | |
Human Event Repository and Analysis (HERA) System, Overview | |
Evaluation of the Broadband Impedance Spectroscopy Prognostic/Diagnostic Technique for Electric Cables Used in Nuclear Power Plants | |
Report of Experimental Results for the International Fire Model Benchmarking and Validation Exercise #3 | |
Containment Integrity Research at Sandia National Laboratories - An Overview | |
Crack Growth Rates of Nickel Alloy Welds in a PWR Environment | |
Effect of LWR Water Environments on the Fatigue Life of Reactor Materials | |
Alternative Conceptual Models for Assessing Food Chain Pathways in Biosphere Models | |
Tests of Uranium (VI) Adsorption Models in a Field Setting | |
GSI-191 PWR Sump Screen Blockage Chemical Effects Tests: Thermodynamic Simulations | |
Chemical Effects Head-Loss Research In Support of Generic Safety Issue 191 | |
Integrated Chemical Effects Test Project | |
Aluminum Chemistry in a Prototypical Post-Loss-of-Coolant-Accident, Pressurized-Water-Reactor Containment Environment | |
Hydraulic Transport of Coating Debris | |
Experimental Measurements of Pressure Drop Across Sump Screen Debris Beds in Support of Generic Safety Issue 191 | |
VARSKIN: A Computer Code for Skin Contamination and Dosimetry Assessments | |
Recommendations for Revision of Seismic Damping Values in Regulatory Guide 1.61 | |
Risk-Informed Assessment of Degraded Containment Vessels | |
Crack Growth Rates in a PWR Environment of Nickel Alloys from the Davis-Besse and V.C. Summer Power Plants | |
P-CARES: Probabilistic Computer Analysis for Rapid Evaluation of Structures | |
Expert Panel Report on Proactive Materials Degradation Assessment | |
Non-destructive and Failure Evaluation of Tubing from a Retired Steam Generator | |
Assessment of Analysis Methods for Seismic Shear Wall Capacity Using JNES/NUPEC Multi-Axial Cyclic and Shaking Table Test Data | |
Evaluation of the Seismic Design Criteria in ASCE/SEI Standard 43-05 for Application to Nuclear Power Plants | |
Primer on Durability of Nuclear Power Plant Reinforced Concrete Structures - A Review of Pertinent Factors | |
Industry-Average Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants | |
Assessment of Eddy Current Testing for the Detection of Cracks in Cast Stainless Steel Reactor Piping Components | |
Temperature Dependence of Weibull Stress Parameters: Studies Using the Euro-Material Similar to ASME A508 Class-3 Steel | |
Carolfire Test Report | |
Baseline Risk Index for Initiating Events (BRIIE) | |
Assessment of Crack Detection in Heavy-Walled Cast Stainless Steel Piping Welds Using Advanced Low-Frequency Ultrasonic Methods | |
Fatigue Crack Flaw Tolerance in Nuclear Power Plant Piping - A Basis for Improvements to ASME Code Section XI Appendix L | |
Sensitivity Studies of Failure of Steam Generator Tubes during Main Steam Line Break and Other Secondary Side Depressurization Events | |
Probabilities of Failure and Uncertainty Estimate Information for Passive Components – A Literature Review | |
Final Report-Assessment of Potential Phosphate Ion-Cenmentitious Materials Interactions | |
Coexistence Assessment of Industrial Wireless Protocols in the Nuclear Facility Environment | |
Combined Estimation of Hydrogeologic Conceptual Model, Parameter, and Scenario Uncertainty with Application to Uranium Transport at the Hanford Site 300 Area | |
Soil-to-Plant Concentration Ratios for Assessing Food-Chain Pathways in Biosphere Models | |
Dynamic Reliability Modeling of Digital Instrumentation and Control Systems for Nuclear Reactor Probabilistic Risk Assessments | |
A Study of Remote Visual Methods to Detect Cracking in Reactor Components | |
Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) | |
Fabrication Flaw Density and Distribution in Repairs to Reactor Pressure Vessel and Piping Welds | |
Field Studies to Confirm Uncertainty Estimates of Ground-Water Recharge | |
Human Factors Considerations with Respect to Emerging Technology in Nuclear Power Plants | |
Integrated Ground-Water Monitoring Strategy for NRC-Licensed Facilities and Sites: Logic, Strategic Approach and Discussion | |
The Employment of Empirical Data and Bayesian Methods in Human Reliability Analysis: A Feasibility Study | |
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit | |
Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) | |
Review of NUREG-0654, Supplement 3, "Criteria for Protective Action Recommendations for Severe Accidents" | |
Fracture Analysis of Vessels - Oak Ridge FAVOR, v04.1, Computer Code: Theory and Implementation of Algorithms, Methods, and Correlations | |
Criticality Analysis of Assembly Misload in a PWR Burnup Credit Cask | |
Nonlinear Analyses for Embedded Cracks Under Pressurized Thermal Shock: Comparisons with FAVOR and Weibull Stress Approaches | |
Correlation Analysis of JNES Seismic Wall Pressure Data for ABWR Model Structures | |
LAPUR 6.0 Manual | |
Application of Surface Complexation Modeling to Selected Radionuclides and Aquifer Sediments | |
Crack Growth Rates and Fracture Toughness of Irradiated Austenitic Stainless Steels in BWR Environments | |
Traditional Probabilistic Risk Assessment Methods for Digital Systems | |
An Assessment of PWR Steam Generator Condensation at the Oregon State University APEX Facility | |
Crack Growth Rates and Metallographic Examinations of Alloy 600 and Alloy 82/182 from Field Components and Laboratory Materials Tested in PWR Environments | |
Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels and Alloy 690 from Halden Phase-II Irradiations | |
Tsunami Hazard Assessment at Nuclear Power Plant Sites in the United States of America | |
Cladding Embrittlement During Postulated Loss-of-Coolant Accidents | |
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation – Calvert Cliffs, Takahama, and Three Mile Island Reactors | |
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation — ARIANE and REBUS Programs | |
Spent Fuel Decay Heat Measurements Performed at the Swedish Central Interim Storage Facility | |
Validation of SCALE 5 Decay Heat Predictions for LWR Spent Nuclear Fuel | |
Technical Basis for Assessing Uranium Bioremediation Performance | |
Symbolic Nuclear Analysis Package (SNAP): Common Application Framework for Engineering Analysis (CAFEAN) Preprocessor Plug-in Application Programming Interface | |
Rod Bundle Heat Transfer Test Facility Test Plan and Design | |
Rod Bundle Heat Transfer Test Facility Description | |
Redox and Sorption Reactions of Iodine and Cesium During Transport Through Aquifer Sediments | |
A Phenomena Identification and Ranking Table (PIRT) Exercise for Nuclear Power Plant Fire Modeling Applications | |
Evaluation of the French Haut Taux de Combustion (HTC) Critical Experiment Data | |
RBHT Reflood Heat Transfer Experiments Data and Analysis | |
Assessment of Emergency Response Planning and Implementation for Large Scale Evacuations | |
Assessment of Noise Level for Eddy Current Inspection of Steam Generator Tubes | |
Seismic Analysis of Large-Scale Piping Systems for the JNES-NUPEC Ultimate Strength Piping Test Program | |
Field Evaluation of Low-Frequency SAFT-UT on Cast Stainless Steel and Dissimilar Metal Weld Components | |
A Benchmark Implementation of Two Dynamic Methodologies for the Reliability Modeling of Digital Instrumentation and Control Systems | |
Evaluations of Structural Failure Probabilities and Candidate Inservice Inspection Programs | |
Analysis of Structural Materials Exposed to a Severe Fire Environment | |
Final Report — Evaluation of Chemical Effects Phenomena in Post-LOCA Coolant | |
Methodology for Estimating Fabrication Flaw Density and Distribution – Reactor Pressure Vessel Welds | |
Development and Testing of ENDF/B-VI.8 and ENDF/B-VII.0 Coupled Neutron-Gamma Libraries for SCALE 6 | |
Design Practices for Communications and Workstations in Highly Integrated Control Rooms | |
Instrumentation and Controls in Nuclear Power Plants: An Emerging Technologies Update | |
Argonne Model Boiler Test Results | |
SCDAP/RELAP5 Thermal-Hydraulic Evaluations of the Potential for Containment Bypass During Extended Station Blackout Severe Accident Sequences in a Westinghouse Four-Loop PWR | |
Nondestructive and Destructive Examination Studies on Removed-from-Service Control Rod Drive Mechanism Penetrations | |
Modeling a Digital Feedwater Control System Using Traditional Probabilistic Risk Assessment Methods | |
Review of Information for Spent Nuclear Fuel Burnup Confirmation | |
Technical Basis for a Proposed Expansion of Regulatory Guide 3.54 — Decay Heat Generation in an Independent Spent Fuel Storage Installation | |
Essential Elements of an Electric Cable Condition Monitoring Program | |
Predictive Bias and Sensitivity in NRC Fuel Performance Codes | |
Criteria for Development of Evacuation Time Estimate Studies | |
Background and Derivation of ANS-5.4 Standard Fission Product Release Model | |
Technical Basis for Regulatory Guidance on Design-Basis Hurricane-Borne Missile Speeds for Nuclear Power Plants | |
Technical Basis for Regulatory Guidance on Design-Basis Hurricane Wind Speeds for Nuclear Power Plants | |
Guidelines for Field-Programmable Gate Arrays in Nuclear Power Plant Safety Systems Plant | |
Diversity Strategies for Nuclear Power Plant Instrumentation and Control Systems | |
MELCOR Best Practices as Applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project | |
MACCS Best Practices as Applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project | |
Cable Heat Release, Ignition, and Spread in Tray Installations During Fire (CHRISTIFIRE) | |
Evaluation of Treatment of Effects of Debris in Coolant on ECCS and CSS Performance in Pressurized Water Reactors and Boiling Water Reactors | |
Uncertainties in Predicted Isotopic Compositions for High Burnup PWR Spent Nuclear Fuel | |
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation—Vandellós II Reactor | |
Processes, Properties, and Conditions Controlling In Situ Bioremediation of Uranium in Shallow, Alluvial Aquifers | |
Analysis of JNES Seismic Tests on Degraded Piping | |
Human Reliability Analysis-Informed Insights on Cask Drops | |
Preliminary, Qualitative Human Reliability Analysis for Spent Fuel Handling | |
Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in BWR Environments | |
Results of the Program for the Inspection of Nickel Alloy Components | |
A Subsurface Decision Model for Supporting Environmental Compliance | |
FRAPCON | |
FRAPTRAN | |
Material Property Correlations: Comparisons between FRAPCON, FRAPTRAN, and MATPRO | |
Radionuclide Release from Slag and Concrete Waste Materials, Part I: Conceptual Models of Leaching from Complex Materials and Laboratory Test Methods | |
Application of Model Abstraction Techniques to Simulate Transport in Soils | |
Degradation of LWR Core Internal Materials Due to Neutron Irradiation | |
Engineered Covers for Waste Containment: Changes in Engineering Properties and Implications for Long-Term Performance Assessment | |
Lessons Learned in Detecting, Monitoring, Modeling and Remediating Radioactive Ground-Water Contamination | |
Atmospheric Stress Corrosion Cracking Susceptibility of Welded and Unwelded 304, 304L, and 316L Austenitic Stainless Steels Commonly Used for Dry Cask Storage Containers Exposed to Marine Environments | |
A Compilation of Elevated Temperature Concrete Material Property Data and Information for Use in Assessments of Nuclear Power Plant Reinforced Concrete Structures | |
Developing an Emergency Risk Communication (ERC)/Joint Information Center (JIC) Plan for a Radiological Emergency | |
Guidance on Developing Effective Radiological Risk Communication Messages: Effective Message Mapping and Risk Communication with the Public in Nuclear Plant Emergency Planning Zones | |
Analysis of Severe Railway Accidents Involving Long Duration Fires | |
Analysis of Severe Roadway Accidents Involving Long Duration Fires | |
Industry Performance of Relief Valves at U.S. Commercial Nuclear Power Plants through 2007 | |
Verification of RESRAD-OFFSITE | |
Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Version 8 | |
Evaluation of JNES Equipment Fragility Tests for Use in Seismic Probabilistic Risk Assessments for U.S. Nuclear Power Plants | |
SCALE/TRITON Primer: A Primer for Light Water Reactor Lattice Physics Calculations | |
A Large Scale Validation of a Methodology for Assessing Software Reliability | |
Development of Quantitative Software Reliability Models for Digital Protection Systems of Nuclear Power Plants | |
Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data | |
Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America | |
LAPUR 6.0 Benchmark Against Data from the GENESIS Facility | |
Direct Current Electrical Shorting in Response to Exposure Fire | |
Structural Materials Analyses of the Newhall Pass Tunnel Fire, 2007 | |
Kerite Analysis in Thermal Environment of FIRE (KATE-Fire): Test Results – Final Report | |
Pacific Northwest National Laboratory Investigation of Stress Corrosion Cracking in Nickel-Base Alloys | |
Radionuclide Release from Slag and Concrete Waste Materials – Part 2: Relationship Between Laboratory Tests and Field Leaching | |
Generation of a Broad-Group HTGR Library for Use with SCALE | |
Validation of SCALE for High Temperature Gas-Cooled Reactor Analysis | |
An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses—Isotopic Composition Predictions | |
An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses—Criticality (keff) Predictions | |
State-of-the-Art Reactor Consequence Analyses Project | |
A Summary of Aging Effects and Their Management in Reactor Spent Fuel Pools, Refueling Cavities, Tori, and Safety-Related Concrete Structures | |
An Assessment of Ultrasonic Techniques for Far-Side Examinations of Austenitic Stainless Steel Piping Welds | |
A Framework for Low Power/Shutdown Fire PRA | |
Performance of Metal and Polymeric O-Ring Seals in Beyond-Design-Basis Temperature Excursions | |
Materials Aging Issues and Aging Management for Extended Storage and Transportation of Spent Nuclear Fuel | |
Secure Network Design | |
Experimental Studies of Reinforced Concrete Structures Under Multi-Directional Earthquakes and Design Implications | |
Radionuclide Behavior in Soils and Soil-to-Plant Concentration Ratios for Assessing Food Chain Pathways | |
An Evaluation of Ultrasonic Phased Array Testing for Cast Austenitic Stainless Steel Pressurizer Surge Line Piping Welds | |
A Literature Review of the Effects of Smoke from a Fire on Electrical Equipment | |
Validation of LAPUR 6.0 Code | |
Human-Performance Issues Related to the Design and Operation of Small Modular Reactors | |
New Source Term Model for the RESRAD-OFFSITE Code Version 3 | |
Void Swelling and Microstructure of Austenitic Stainless Steels Irradiated in the BOR-60 Reactor | |
Review of Probable Maximum Precipitation Procedures and Databases Used to Develop Hydrometeorological Reports | |
Application of Radar-Rainfall Estimates to Probable Maximum Precipitation in the Carolinas | |
Synthesis of Extreme Storm Rainfall and Probable Maximum Precipitation in the Southeastern U.S. Pilot Region | |
The Estimation of Very-Low Probability Hurricane Storm Surges for Design and Licensing of Nuclear Power Plants in Coastal Areas | |
Compensatory and Alternative Regulatory MEasures for Nuclear Power Plant FIRE Protection (CARMEN-FIRE) | |
Assessment of NDE Methods on Inspection of HDPE Butt Fusion Piping Joints for Lack of Fusion | |
Stress Corrosion Cracking in Nickel-Base Alloys 690 and 152 Weld in Simulated PWR Environment - 2009 | |
Assessment of Current Test Methods for Post-LOCA Cladding Behavior | |
The U.S. Nuclear Regulatory Commission's Cyber Security Regulatory Framework for Nuclear Power Reactors | |
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 | |
Characterization of Thermal-Hydraulic and Ignition Phenomena in Prototypic, Full-Length Boiling Water Reactor Spent Fuel Pool Assemblies After a Postulated Complete Loss-of-Coolant Accident | |
Laminar Hydraulic Analysis of a Commercial Pressurized Water Reactor Fuel Assembly | |
Nuclear Power Plant Security Assessment Guide | |
Confirmatory Battery Testing: The Use of Float Current Monitoring to Determine Battery State-of-Charge | |
Effects of Degradation on the Severe Accident Consequences for a PWR Plant with a Reinforced Concrete Containment Vessel | |
Joint Assessment of Cable Damage and Quantification of Effects from Fire (JACQUE-FIRE) – Final Report | |
Development of a Fault Injection-Based Dependability Assessment Methodology for Digital I&C Systems | |
Rod Bundle Heat Transfer Facility – Steady-State Steam Cooling Experiments | |
Expanded Materials Degradation Assessment (EMDA) | |
Risk Informing Emergency Preparedness Oversight: Evaluation of Emergency Action Levels — A Pilot Study of Peach Bottom, Surry and Sequoyah | |
State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analysis of the Unmitigated Long-Term Station Blackout of the Peach Bottom Atomic Power Station | |
Fitness for Duty in the Nuclear Power Industry: An Update of Technical Issues on Drugs of Abuse Testing and Fatigue Management | |
Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit | |
Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel | |
Reliability of Ultrasonic In-Service Inspection of Welds in Reactor Internals of Boiling Water Reactors | |
Emergency Preparedness Significance Quantification Process: Proof of Concept | |
Synthesis of Distributions Representing Important Non-Site-Specific Parameters in Off-Site Consequence Analyses | |
Analysis of Experimental Data for High Burnup BWR Spent Fuel Isotopic Validation – SVEA-96 and GE14 Assembly Designs | |
A Formalized Approach for the Collection of HRA Data from Nuclear Power Plant Simulators | |
Cross Section Generation Guidelines for TRACE–PARCS | |
The Technical Basis Supporting ASME Code, Section XI, Appendix VIII: Performance Demonstration for Ultrasonic Examination Systems | |
Radiological Toolbox User's Guide | |
Assessing the Potential for Biorestoration of Uranium In Situ Recovery Sites | |
Regulatory Approaches for Addressing Reprocessing Facility Risks: An Assessment | |
Sensors and Monitoring to Assess Grout and Vault Behavior for Performance Assessment | |
Assessment of Stress Corrosion Cracking Susceptibility for Austenitic Stainless Steels Exposed to Atmospheric Chloride and Non-Chloride Salts | |
A Review of the Effects of Radiation on Microstructure and Properties of Concretes Used in Nuclear Power Plants | |
Knowledge Base Report on Emergency Core Cooling Sump Performance in Operating Light Water Reactors | |
Transfer Factors for Contaminant Uptake by Fruit and Nut Trees | |
Susceptibility of Nuclear Stations to External Faults | |
Safety and Regulatory Issues of the Thorium Fuel Cycle | |
Compendium of Analyses to Investigate Select Level 1 Probabilistic Risk Assessment End-State Definition and Success Criteria Modeling Issues | |
Uranium Sequestration During Biostimulated Reduction and In Response to the Return of Oxic Conditions In Shallow Aquifers | |
BWR Anticipated Transients Without Scram in the MELLLA+ Expanded Operating Domain, Part 1: Model Development and Events | |
BWR Anticipated Transients Without Scram in the MELLLA+ Expanded Operating Domain, Part 2: Sensitivity Studies for Events Leading to Instability | |
BWR Anticipated Transients Without Scram in the MELLLA+ Expanded Operating Domain, Part 3: Events Leading to Emergency Depressurization | |
BWR Anticipated Transients Without Scram in the MELLLA+ Expanded Operating Domain, Part 4: Sensitivity Studies for Events Leading to Emergency Depressurization | |
Best Practices for Behavioral Observation Programs at Operating Power Reactors and Power Reactor Construction Sites | |
Crack Growth Rate and Fracture Toughness Tests on Irradiated Cast Stainless Steels | |
Effect of Thermal Aging and Neutron Irradiation on Crack Growth Rate and Fracture Toughness of Cast Stainless Steels and Austenitic Stainless Steel Welds | |
Experimental Measurement of Suppression Pool Void Distribution During Blowdown in Support of Generic Issue 193 | |
Managing PWSCC in Butt Welds by Mitigation and Inspection | |
Testing to Evaluate Extended Battery Operation in Nuclear Power Plants | |
User's Guide for RESRAD-OFFSITE | |
Workload, Situation Awareness, and Teamwork | |
Thermal Analysis of Horizontal Storage Casks for Extended Storage Applications | |
Rod Bundle Heat Transfer Facility Steam Cooling with Droplet Injection Experiments Data Report | |
Evaluations of NRC Seismic-Structural Regulations and Regulatory Guidance, and Simulation-Evaluation Tools for Applicability to Small Modular Reactors (SMRs) | |
Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems | |
Risk-Informed and Performance-Based Oversight of Radiological Emergency Response Programs | |
Large Scale Earthquake Simulation of a Hybrid Lead Rubber Isolation System Designed with Consideration of Nuclear Seismicity | |
Heat Release Rates of Electrical Enclosure Fires (HELEN-FIRE) | |
Mechanical Fatigue Testing of High-Burnup Fuel for Transportation Applications | |
Radionuclide Release from Slag and Concrete Waste Materials – Part 3: Testing Protocol | |
Influence of Coupling Erosion and Hydrology on the Long-Term Performance of Engineered Surface Barriers | |
Characterizing Explosive Effects on Underground Structures | |
NRC Reviewer Aid for Evaluating the Human-Performance Aspects Related to the Design and Operation of Small Modular Reactors | |
A Quantitative Impact Assessment of Hypothetical Spent Fuel Reconfiguration in Spent Fuel Storage Casks and Transportation Packages | |
Applying Ultrasonic Testing in Lieu of Radiography for Volumetric Examination of Carbon Steel Piping | |
Bias Estimates Used in Lieu of Validation of Fission Products and Minor Actinides in MCNP Keff Calculations for PWR Burnup Credit Casks | |
Spent Fuel Transportation Package Response to the MacArthur Maze Fire Scenario | |
Spent Fuel Transportation Package Response to the Newhall Pass Tunnel Fire Scenario | |
Study on Post Tensioning Methods | |
A Compendium of Spent Fuel Transportation Package Response Analyses to Severe Fire Accident Scenarios | |
Development and Validation of Models for Predicting Leakage from Degraded Tube-to-Tubesheet Joints During Severe Accidents | |
Application of a Hydrological Uncertainty Methodology to Nuclear Reactor Site Evaluations | |
Technical Manual and User's Guide for MILDOS-AREA Version 4 | |
MILDOS-AREA Computation Verification Version 4 | |
Toward a More Risk-Informed and Performance-Based Framework for the Regulation of the Seismic Safety of Nuclear Power Plants | |
Spent Fuel Pool Project Phase 1: Pre-Ignition and Ignition Testing of a Single Commercial 17x17 Pressurized Water Reactor Spent Fuel Assembly under Complete Loss of Coolant Accident Conditions | |
Spent Fuel Pool Project Phase II: Pre-Ignition and Ignition Testing of a 1x4 Commercial 17x17 Pressurized Water Reactor Spent Fuel Assemblies under Complete Loss of Coolant Accident Conditions | |
Application of Automated Analysis Software to Eddy Current Inspection Data from Steam Generator Tube Bundle Mock-up | |
Rod Bundle Heat Transfer Facility Two-Phase Mixture Level Swell and Uncovery Test Experiments Data Report | |
Cladding Behavior during Postulated Loss-of-Coolant Accidents | |
SNAP/RADTRAD 4.0: Description of Models and Methods | |
Integrating Model Abstraction into Subsurface Monitoring Strategies | |
Tsunami Hazard Assessment Based on Wave Generation, Propagation, and Inundation Modeling for the U.S. East Coast | |
Tsunami Hazard Assessment: Best Modeling Practices and State-of-the-Art Technology | |
Axial Moderator Density Distributions, Control Blade Usage, and Axial Burnup Distributions for Extended BWR Burnup Credit | |
Stability of Circumferential Flaws in Once-Through Steam Generator Tubes Under Thermal Loading During LOCA, MSLB and FWLB | |
Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Base Welds Near Dissimilar Metal Weld Interfaces | |
US Commercial Spent Nuclear Fuel Assembly Characteristics: 1968-2013 | |
Open Secondary Testing of Window-Type Current Transformers | |
Testing to Evaluate Battery and Battery Charger Short-Circuit Current Contributions to a Fault on the DC Distribution System | |
Seismic Design Standards and Calculational Methods in the United States and Japan | |
Modeling of Radionuclide Transport in Freshwater Systems Associated with Nuclear Power Plants | |
Review of Spent Fuel Reprocessing and Associated Accident Phenomena | |
Developing a Bayesian Belief Network Model for Quantifying the Probability of Software Failure of a Protection System | |
Development of A Statistical Testing Approach for Quantifying Safety-Related Digital System on Demand Failure Probability | |
Results of Blind Testing for the Program to Assess the Reliability of Emerging Nondestructive Techniques | |
Results of Open Testing for the Program to Assess the Reliability of Emerging Nondestructive Techniques | |
Correlation of Seismic Performance in Similar SSCs (Structures, Systems, and Components) | |
Guidance Document: Conducting Paleoliquefaction Studies for Earthquake Source Characterization | |
Review of Exemptions and General Licenses for Fissile Material in 10 CFR 71 | |
Impact of Operating Parameters on Extended BWR Burnup Credit | |
PIMAL: Phantom with Moving Arms and Legs – Version 4.1.0 | |
Response of Nuclear Power Plant Instrumentation Cables Exposed to Fire Conditions | |
State-of-the-Art Reactor Consequence Analyses (SOARCA) Project: Sequoyah Integrated Deterministic and Uncertainty Analyses | |
Reliability Assessment of Remote Visual Examination | |
Capabilities and Practices of Offsite Response Organizations for Protective Actions in the Intermediate Phase of a Radiological Emergency Response | |
Overview of Nuclear Data Uncertainty in Scale and Application to Light Water Reactor Uncertainty Analysis | |
Thermal-Hydraulic Experiments Using A Dry Cask Simulator | |
Margins for Uncertainty in the Predicted Spent Fuel Isotopic Inventories for BWR Burnup Credit | |
Validation of keff Calculations for Extended BWR Burnup Credit | |
Technical Considerations for Seismic Isolation of Nuclear Facilities | |
Seismic Isolation of Nuclear Power Plants Using Sliding Bearings | |
Seismic Isolation of Nuclear Power Plants using Elastomeric Bearings | |
Effects of Environmental Conditions on Manual Actions for Flood Protection and Mitigation | |
Paleoliquefaction Studies in Moderate Seismicity Regions with a History of Large Events | |
Technical Manual and User’s Guide for MILDOS, Version 4.1 | |
MILDOS Version 4.1 Computational Verification Report | |
CFD Validation of Vertical Dry Cask Storage System | |
State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analysis of the Unmitigated Short-Term Station Blackout of the Surry Power Station | |
NDE Reliability Issues for the Examination of CASS Components | |
Managing the Effects of Degraded Digital Instrumentation and Control Conditions on Operator Performance: Human Factors Engineering Review Guidance Development | |
Phenomena Identification and Ranking Technique (PIRT) Exercise for Ranking Low-Power Shutdown Plant Operating States and Outage Types | |
MELCOR Modeling of Accident Scenarios at a Facility for Aqueous Reprocessing of Spent Nuclear Fuel | |
Default Parameter Values and Distribution in RESRAD-ONSITE V7.2, RESRAD-BUILD V3.5, and RESRAD-OFFSITE V4.0 Computer Codes | |
User's Manual for RESRAD-OFFSITE Code Version 4 | |
Enhancing Guidance for Evacuation Time Estimate Studies | |
Technical Bases for Consequence Analyses Using MACCS (MELCOR Accident Consequence Code System) | |
Application of Point Precipitation Frequency Estimates to Watersheds | |
NRC ATWS-I Stability Tests with Downskew Axial Power Profile: KATHY Test Series STS123 | |
Developing a Technical Basis for Embedded Digital Devices and Emerging Technologies | |
Validation of a Computational Fluid Dynamics Method Using Horizontal Dry Cask Simulator Data | |
Jet Impingement in High-Energy Piping Systems | |
Primary Water Stress Corrosion Cracking of High-Chromium Nickel-Base Welds – 2018 | |
Primary Water Stress Corrosion Cracking of High-Chromium Nickel-Base Welds at or Near Interfaces – 2020 | |
Technical Basis for the use of Probabilistic Fracture Mechanics in Regulatory Applications | |
Research to Develop Flood Barrier Testing Strategies for Nuclear Power Plants | |
Review of Radiation-Induced Concrete Degradation and Potential Implications for Structures Exposed to High Long-Term Radiation Levels in Nuclear Power Plants | |
Radiation Evaluation Methodology for Concrete Structures | |
Review of Accident Tolerant Fuel Concepts with Implications to Severe Accident Progression and Radiological Releases | |
Phenomena Identification Ranking Tables for Accident Tolerant Fuel Designs Applicable to Severe Accident Conditions | |
SCALE 6.2 Lattice Physics Performance Assessment | |
Nonradiological Health Consequences from Evacuation and Relocation | |
Reactor Pressure Vessel Fluence Evaluation Methodology for Extended Beltline Locations | |
Numerical Modeling of Local Intense Precipitation Processes | |
Evaluation of In-Service Radon Barriers over Uranium Mill Tailings Disposal Facilities | |
Nuclear Data Assessment for Advanced Reactors | |
Convection-Permitting Modeling for Intense Precipitation Processes | |
Assessments on Eddy Current Detection of Cracking Near Volumetric Indications in Steam Generator Tubes | |
The Price-Anderson Act: 2021 Report to Congress, Public Liability Insurance and Indemnity Requirements for an Evolving Commercial Nuclear Industry Office | |
Exploring Advanced Computational Tools and Techniques with Artificial Intelligence and Machine Learning in Operating Nuclear Plants | |
Human Factors in Nondestructive Examination | |
Multi-Mechanism Flood Hazard Assessment: Critical Review of Current Practice and Approaches and Example Use Studies | |
Basis for Technical Guidance To Evaluate Evapotranspiration Covers | |
Fuel Qualification for Molten Salt Reactors | |
Radiation Accident Dose and Simulated Loss-of-Coolant Accident Test of Low Voltage Cables | |
Ultrasonic Modeling and Simulation for Nuclear Nondestructive Evaluation | |
Updated Recommendations Related to Spent Fuel Transport and Dry Storage Shielding Analyses | |
Validating Actinides and Fission Products for Burnup Credit Criticality Safety Analyses - Nuclide Compositions Prediction with Extended Validation Basis | |
Evaluating Flaw Detectability Under Limited-Coverage Conditions | |
Metal Fuel Qualification: Fuel Assessment Using NRC NUREG-2246, "Fuel Qualification for Advanced Reactors" | |
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 | |
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 | |
Sensitivity/Uncertainty Methods for Nuclear Criticality Safety Validation | |
Validation Studies for High Burnup and Extended Enrichment Fuels in Burnup Credit Criticality Safety Analyses | |
Spent Fuel Storage and Transportation of Accident Tolerant Concepts: Cr-Coated Zirconium Alloy Cladding, FeCrAl Cladding, High Burnup and High Enrichment Fuel | |
Determination of Bias and Bias Uncertainty for Criticality Safety Computational Methods | |
Irradiation Effects on Reinforced Concrete Structures – Experimental and Analytical Study on Irradiated Concrete – Steel Bonding, Modeling and Simulation of Structural Response |
Page Last Reviewed/Updated Monday, December 22, 2025
Page Last Reviewed/Updated Monday, December 22, 2025