The U.S. Nuclear Regulatory Commission (NRC) provides guidance to licensees and applicants by issuing NUREG-series publications regarding regulatory decisions, research results, results of incident investigations, and other technical and administrative information. NUREG-series publications disseminate scientific, technical, and administrative information dealing with licensing and regulation of civilian nuclear facilities and materials. Publications in the NUREG series may neither state nor imply any regulatory requirements, since such requirements are stated only in laws, regulations, licenses (including technical specifications), or orders. In other words, the NRC staff may suggest a course of action in a NUREG-series publication, but the regulated community may use other approaches to satisfy the agency’s regulatory requirements.
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-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-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-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-6410 |
Nuclear Fuel Cycle Facility Accident Analysis Handbook |
NUREG/CR-6444 |
Methodology for Analyzing Precursors to Earthquake-Initiated and Fire-Initiated Accident Sequences |
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 |