| Document Identifier |
Title |
| NUREG/CR-0152 |
Development and Verification of Fire Tests for Cable Systems and System Components |
| NUREG/CR-0381 |
A Preliminary Report on Fire Protection Research Program Fire Barriers and Fire Retardant Coatings Tests |
| NUREG/CR-0468 |
Nuclear Power Plant Fire Protection - Fire Barriers |
| NUREG/CR-0488 |
Nuclear Power Plant Fire Protection - Fire Detection |
| NUREG/CR-0596 |
A Preliminary Report on Fire Protection Research Program, Fire Barriers and Suppression |
| NUREG/CR-0636 |
Nuclear Power Plant Fire Protection - Ventilation |
| NUREG/CR-0654 |
Nuclear Power Plant Fire Protection - Fire-Hazards Analysis |
| NUREG/CR-0833 |
Fire Protection Research Program Corner Effects Tests |
| NUREG/CR-1156 |
Environmental Assessment of Ionization Chamber Smoke Detectors Containing Am-241 |
| NUREG/CR-1184 |
Evaluation of Simulator Adequacy for the Radiation Qualification of Safety-Related Equipment |
| NUREG/CR-1405 |
The NACOM Code for Analysis of Postulated Sodium Spray Fires in LMFBRs |
| NUREG/CR-1552 |
Development and Verification of Fire Tests for Cable Systems and System Components |
| NUREG/CR-1614 |
Approaches to Acceptable Risk: A Critical Guide |
| NUREG/CR-1682 |
Electrical Insulators in a Reactor Accident Environment |
| NUREG/CR-1798 |
Acceptance and Verification For Early Warning Fire Detection Systems |
| NUREG/CR-1819 |
Development and Testing Of A Model for Fire Potential in Nuclear Power Plants |
| NUREG/CR-1916 |
A Risk Comparison |
| NUREG/CR-1930 |
Index of Risk Exposure and Risk Acceptance Criteria |
| NUREG/CR-2040 |
A Study of the Implications of Applying Quantitative Risk Criteria in the Licensing of Nuclear Power Plants in the United States |
| NUREG/CR-2258 |
Fire Risk Analysis for Nuclear Power Plants |
| NUREG/CR-2269 |
Probabilistic Models for the Behavior of Compartment Fires |
| NUREG/CR-2300 |
PRA Procedures Guide: A Guide to the Performance of Probabilistic Risk Assessments for Nuclear Power Plants |
| NUREG/CR-2321 |
Investigation of Fire Stop Test Parameters Final Report |
| NUREG/CR-2377 |
Test and Criteria for Fire Protection Of Cable Penetrations |
| NUREG/CR-2409 |
Requirements for Establishing Detector Siting Criteria in Fires Involving Electrical Materials |
| NUREG/CR-2431 |
Burn Mode Analysis of Horizontal Cable Tray Fires |
| NUREG/CR-2475 |
Hydrogen Combustion Characteristics Related to Reactor Accidents |
| NUREG/CR-2486 |
Final Results of the Hydrogen Igniter Experimental Program |
| NUREG/CR-2490 |
Hazards to Nuclear Power Plants from Large Liquefied Natural Gas (LNG) Spills on Water |
| NUREG/CR-2607 |
Fire Protection Research Program for the U. S. Nuclear Regulatory Commission 1975-1981 |
| NUREG/CR-2650 |
Allowable Shipment Frequencies for the Transport of Toxic Gases Near Nuclear Power Plants |
| NUREG/CR-2658 |
Characteristics of Combustion Products: A Review of the Literature |
| NUREG/CR-2726 |
Light Water Reactor Hydrogen Manual |
| NUREG/CR-2730 |
Hydrogen Burn Survival: Preliminary Thermal Model and Test Results |
| NUREG/CR-2815 |
Probabilistic Safety Analysis Procedures Guide |
| NUREG/CR-2868 |
Aging Effects on Fire-Retardant Additives in Organic Materials for Nuclear Plant Applications |
| NUREG/CR-2927 |
Nuclear Power Plant Electrical Cable Damageability Experiments |
| NUREG/CR-3037 |
A Computer Code to Estimate Accidental Fire and Airborne Releases in Nuclear Fuel Cycle Facilities Radioactive |
| NUREG/CR-3122 |
Potentially Damaging Failure Modes of High- and Medium-Voltage Electrical Equipment |
| NUREG/CR-3139 |
Scenarios and Analytical Methods for UF6 Releases at NRC-Licensed Fuel Cycle Facilities |
| NUREG/CR-3192 |
Investigation of Twenty-Foot Separation Distance as a Fire Protection Method as Specified in 10 CFR 50, Appendix R |
| NUREG/CR-3239 |
COMPBRN - A Computer Code for Modeling Compartment Fires |
| NUREG/CR-3242 |
The Los Alamos National Laboratory/New Mexico State University Filter Plugging Test Facility Description and Preliminary Test Results |
| NUREG/CR-3263 |
Status Report: Correlation of Electrical Cable Failure with Mechanical Degradation |
| NUREG/CR-3330 |
Vulnerability of Nuclear Power Plant Structures to Large External Fires |
| NUREG/CR-3385 |
Measures of Risk Importance And Their Applications |
| NUREG/CR-3468 |
Hydrogen: Air: Steam Flammability Limits and Combustion Characteristics in the FITS Vessel |
| NUREG/CR-3493 |
A Review of the Limerick Generating Station Severe Accident Risk Assessment |
| NUREG/CR-3521 |
Hydrogen-Burn Survival Experiments at Fully Instrumented Test Site (FITS) |
| NUREG/CR-3527 |
Material Transport Analysis for Accident-Induced Flow in Nuclear Facilities |
| NUREG/CR-3532 |
Response of Rubber Insulation Materials to Monoenergetic Electron Irradiations |
| NUREG/CR-3629 |
The Effect of Thermal and Irradiation Aging Simulation Procedures on Polymer Properties |
| NUREG/CR-3638 |
Hydrogen-Steam Jet-Flame Facility and Experiments |
| NUREG/CR-3656 |
Evaluation of Suppression Methods for Electrical Cable Fires |
| NUREG/CR-3719 |
Detonation Calculations Using a Modified Version of CSQII: Examples for Hydrogen-Air Mixtures |
| NUREG/CR-3735 |
Accident-Induced Flow and Material Transport in Nuclear Facilities-A Literature Review |
| NUREG/CR-3922 |
Survey and Evaluation of System Interaction Events and Sources |
| NUREG/CR-4112 |
Investigation of Cable and Cable System Fire Test Parameters |
| NUREG/CR-4138 |
Data Analyses for Nevada Test Site (NTS) Premixed Combustion Tests |
| NUREG/CR-4229 |
Evaluation of Current Methodology Employed in Probabilistic Risk Assessment (PRA) of Fire Events at Nuclear Power Plants |
| NUREG/CR-4230 |
Probability-Based Evaluation of Selected Fire Protection Features in Nuclear Power Plants |
| NUREG/CR-4231 |
Evaluation of Available Data, for, Probabilistic Risk Assessments (PRA) of Fire Events at Nuclear Power Plants |
| NUREG/CR-4264 |
Investigation of High-efficiency Particulate Air Filter Plugging by Combustion Aerosols |
| NUREG/CR-4310 |
Investigation of Potential Fire-Related Damage to Safety-Related Equipment in Nuclear Power Plants |
| NUREG/CR-4321 |
Full-Scale Measurements of Smoke Transport and Deposition in Ventilation System Ductwork |
| NUREG/CR-4330 |
Review of Light Water Reactor Regulatory Requirements Identification of Regulatory Requirements That May Have Marginal Importance To Risk |
| NUREG/CR-4479 |
The Use of a Field Model to Assess Fire Behavior in Complex Nuclear Power Plant Enclosures: Present Capabilities and Future Prospects |
| NUREG/CR-4517 |
Design Features for Enhancing International Safeguards of Away-from- Reactor Dry Storage for Spent LWR Fuel |
| NUREG/CR-4527 |
An Experimental Investigation of Internally Ignited Fires in Nuclear Power Plant Control Cabinets |
| NUREG/CR-4534 |
Analysis of Diffusion Flame Tests |
| NUREG/CR-4561 |
FIRAC User's Manual: A Computer Code to Simulate Fire Accidents in Nuclear Facilities |
| NUREG/CR-4566 |
COMPBRN III - A Computer Code for Modeling Compartment Fires |
| NUREG/CR-4570 |
Description and Testing of an Apparatus for Electrically Initiating Fires Through Simulation of a Faulty Connection |
| NUREG/CR-4586 |
User Guide for a Personal-Computer-Based Nuclear Power Plan Fire Data Base |
| NUREG/CR-4596 |
Screening Tests of Representative Nuclear Power Plant Components Exposed to Secondary Environments Created by Fires |
| NUREG/CR-4638 |
Transient Fire Environment Cable Damageability Test Results |
| NUREG/CR-4679 |
Quantitative Data on the Fire Behavior of Combustible Materials Found in Nuclear Power Plants: A Literature Review |
| NUREG/CR-4680 |
Heat and Mass Release for Some Transient Fuel Source Fires: A Test Report |
| NUREG/CR-4681 |
Enclosure Environment Characterization Testing for the Base Line Validation of Computer Fire Simulation Codes |
| NUREG/CR-4736 |
Combustion Aerosols Formed During Burning of Radioactively Contaminated Materials, Experimental Results |
| NUREG/CR-4829 |
Shipping Container Response to Severe Highway and Railway Accident Conditions |
| NUREG/CR-4830 |
MELCOR Validation and Verification: 1986 Papers |
| NUREG/CR-4839 |
Methods for External Event Screening Quantification: Risk Methods Integration and Evaluation Program (RMIEP) Methods Development |
| NUREG/CR-4840 |
Procedures for the External Event Core Damage Frequency Analyses for NUREG-1150 |
| NUREG/CR-4855 |
Development and Application of a Computer Model for Large-Scale Flame Acceleration Experiments |
| NUREG/CR-4905 |
Detonability of H2-Air-Diluent Mixtures |
| NUREG/CR-5037 |
Fire Environment Determination in the LaSalle Nuclear Power Plant Control Rroom |
| NUREG/CR-5079 |
Experimental Results Pertaining to the Performance of Thermal Igniters |
| NUREG/CR-5233 |
A Computer Code for Fire Protection and Risk Analysis of Nuclear Plants |
| NUREG/CR-5275 |
FLAME Facility: The Effect of Obstacles and Transverse Venting on Flame Acceleration and Transition to Detonation for Hydrogen-Air Mixtures at Large Scale |
| NUREG/CR-5281 |
Value/Impact Analyses of Accident Preventive and Mitigative Options for Spent Fuel Pools |
| NUREG/CR-5384 |
A Summary of Nuclear Power Plant Fire Safety Research at Sandia National Laboratories, 1975-1987 |
| NUREG/CR-5457 |
A Review of the Three Mile Island-1 Probabilistic Risk Assessment |
| NUREG/CR-5525 |
Hydrogen-Air-Diluent Detonation Study for Nuclear Reactor Safety Analyses |
| NUREG/CR-5546 |
An Investigation of the Effects of Thermal Aging on, the Fire Damageability of Electric Cables |
| NUREG/CR-5580 |
Evaluation of Generic Issue 57 |
| NUREG/CR-5619 |
The Impact of Thermal Aging on the Flammability of Electric Cables |
| NUREG/CR-5655 |
Submergence and High-Temperature Steam Testing of Class 1E Electrical Cables |
| NUREG/CR-5669 |
Evaluation of Exposure Limits to Toxic Gases for Nuclear Reactor Control Room Operators |
| NUREG/CR-5789 |
Risk Evaluation for a Westinghouse PWR, Effects of Fire Protection System Actuation on Safety-Related Equipment: Evaluation of Generic Issue 57 |
| NUREG/CR-5790 |
Risk Evaluation for a B&W Pressurized Water Reactor, Effects of Fire Protection System Actuation on Safety-Related Equipment: Evaluation of Generic Issue 57 |
| NUREG/CR-5791 |
Risk Evaluation for a General Electric BWR, Effects of Fire Protection System Actuation on Safety-Related Equipment: Evaluation of Generic Issue 57 |
| NUREG/CR-6017 |
Fire Modeling of the Heiss Dampf Reaktor Containment |
| NUREG/CR-6042 |
Perspectives on Reactor Safety |
| NUREG/CR-6095 |
Aging, Loss-of-Coolant Accident (LOCA), and High Potential Testing of Damaged Cables |
| NUREG/CR-6173 |
A Summary of the Fire Testing Program at the German HDR Test Facility |
| NUREG/CR-6213 |
High-Temperature Hydrogen-Air- Steam Detonation Experiments in the BNL Small-Scale Development Apparatus |
| NUREG/CR-6220 |
An Assessment of Fire Vulnerability for Aged Electrical Relays |
| NUREG/CR-6358 |
Assessment of United States Industry Structural Codes and Standards for Application to Advanced Nuclear Power Reactors |
| NUREG/CR-6384 |
Literature Review of Environmental Qualification of Safety-Related Electric Cables |
| NUREG/CR-6406 |
Environmental Testing of an Experimental Digital Safety Channel |
| NUREG/CR-6410 |
Nuclear Fuel Cycle Facility Accident Analysis Handbook |
| NUREG/CR-6476 |
Circuit Bridging of Components by Smoke |
| NUREG/CR-6479 |
Technical Basis for Environmental Qualification of Microprocessor-Based Safety-Related Equipment in Nuclear Power Plants |
| NUREG/CR-6509 |
The Effect of Initial Temperature on Flame Acceleration and Deflagration-to-Detonation Transition Phenomenon |
| NUREG/CR-6524 |
The Effect of Lateral Venting on Deflagration-to-Detonation Transition in Hydrogen-Air-Steam Mixtures at Various Initial Temperatures |
| NUREG/CR-6530 |
Deliberate Ignition of Hydrogen-Air-Steam Mixtures in Condensing Steam Environments |
| NUREG/CR-6543 |
Effects of Smoke on Functional Circuits |
| NUREG/CR-6544 |
A Methodology for Analyzing Precursors to Earthquake-Initiated and Fire-Initiated Accident Sequences |
| NUREG/CR-6597 |
Results and Insights on the Impact of Smoke on Digital Instrumentation and Control |
| NUREG/CR-6681 |
Ampacity Derating and Cable Functionality for Raceway Fire Barriers |
| NUREG/CR-6738 |
Risk Methods Insights Gained from Fire Incidents |
| NUREG/CR-6752 |
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 |