Site Map: NRC Library
This page shows how the U.S. Nuclear Regulatory Commission (NRC) has organized the NRC Library, which is available through our public Web site. These links will take you directly to the indicated pages on our site.
- Basic References
- Controlled Unclassified Information Program (CUI)
- Document Collections
- Advisory Committee on Medical Uses of Isotopes
- Advisory Committee on Nuclear Waste and Materials
- Advisory Committee on Reactor Safeguards
- Agreement State Action Items
- Agreement State Communications
- ASLBP
- Commission Documents
- Congressional Documents
- Electronic Government (E-Gov) Documents
- Enforcement Documents
- Enforcement Petition (2.206)
- Events, Reports Associated with
- Fact Sheets & Brochures
- Federal Register Notices (NRC)
- Forms (NRC)
- For the Record
- Generic Communications
- Generic Issues
- Government Information Locator Service (GILS)
- Human Factors Information System
- Inspection Manual
- OIG Reports
- IMPEP Reviews of NRC Programs
- Interim Staff Guidance
- Management Directives
- Memoranda of Understanding
- News Releases
- NMSS Procedures
- NUREG-Series Publications
- Publications Prepared by NRC Staff
- NUREG-0016
- Information Digest, 2024–2025 (NUREG-1350, Volume 35)
- Information on the Confinement Capability of the Facility Disposal Area at West Valley, New York (NU
- NUREG-1480
- NUREG/CR-6210
- NUREG-2238
- Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants
- Safety Evaluation Report: Northwest Medical Isotopes, LLC Construction Permit Application for a Radi
- Methodology for Modeling Fire Growth and Suppression Response for Electrical Cabinet Fires in Nuclea
- Heat Release Rate and Fire Characteristics of Fuels Representative of Typical Transient Fire Events
- Environmental Impact Statement for Interim Storage Partners LLC's License Application for a Consolid
- NUREG-2237
- Methodology for Modeling Transient Fires in Nuclear Power Plant Fire Probabilistic Risk Assessment (
- Final Safety Evaluation Report: Related to the Certification of the Advanced Boiling Water Reactor D
- Confirmatory Thermal-Hydraulic Analysis To Support Specific Success Criteria in the Standardized Pla
- Environmental Impact Statement for the Disposal of Mine Waste at the United Nuclear Corporation Mill
- Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030 – Final Report (NUREG-2242)
- HABIT 2.2 Description of Models and Methods (NUREG-2244)
- The General Methodology of An Integrated Human Event Analysis System (IDHEAS-G) (NUREG-2198)
- Fuel Qualification for Advanced Reactors, Final (NUREG-2246)
- Environmental Impact Statement for the License Renewal of the Columbia Fuel Fabrication Facility in
- Controlling the Atom: The Beginnings of Nuclear Regulation 1946-1962 (NUREG-1610)
- Containing the Atom: Nuclear Regulation in a Changing Environment, 1963-1971 (NUREG-1933)
- Technical Review of the 2017 Edition of ASME Code, Section III, Division 5, "High Temperature Reacto
- Extremely Low Probability of Rupture Version 2 Probabilistic Fracture Mechanics Code (NUREG-2247)
- Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required fo
- Flood Penetration Seal Testing Protocol Research (NUREG-2240)
- Annual Evaluation Plan (NUREG-2250)
- Capacity Assessment: For Statistics, Research, Evaluation, and Other Analysis (NUREG-2251)
- Evidence Building Plan (NUREG-2252)
- Artificial Intelligence Strategic Plan: Fiscal Years 2023-2027 (NUREG-2261)
- Environmental Impact Statement for the Construction Permit for the Kairos Hermes Test Reactor – Fina
- Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project (
- Integrated Human Event Analysis System for Event and Condition Assessment (IDHEAS-ECA) (NUREG-2256)
- Glossary of Security Terms for Nuclear Power Reactors (NUREG-2203)
- Weapons Safety Assessment (NUREG-2264)
- High Energy Arcing Fault Frequency and Consequence Modeling – Final Report (NUREG-2262, EPRI 3002025
- Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Leve
- NRC Program for the Resolution of Generic Issues Related to Nuclear Power Plants (NUREG-0410)
- NRCDose3 Code, Version 1.1.4: User Guide and Technical Manual (NUREG-2267)
- Chemical Process Safety at Fuel Cycle Facilities (NUREG-1601)
- Generic Environmental Impact Statement for Licensing of New Nuclear Reactors – Draft Report for Comm
- Guidance for Conducting Expert Elicitation in Risk-Informed Decisionmaking Activities (NUREG-2255)
- Ruptured Cesium-137 Well-Logging Source at Shelwell Services, Inc., Hebron, Ohio (NUREG-1028)
- Brochures Prepared by NRC Staff
- Conference Proceedings Prepared by NRC Staff or Contractors
- Publications Prepared by NRC Contractors
- Review of Probable Maximum Precipitation Procedures and Databases Used to Develop Hydrometeorologica
- Effects of Environmental Conditions on Manual Actions for Flood Protection and Mitigation (NUREG/CR-
- Enhancing Guidance for Evacuation Time Estimate Studies (NUREG/CR-7269)
- NUREG/CR-7272
- NUREG/CR-7210
- NUREG/CR-7265
- Validation of a Computational Fluid Dynamics Method Using Horizontal Dry Cask Simulator Data
- Application of Point Precipitation Frequency Estimates to Watersheds (NUREG/CR-7271, ORNL/SPR-2019/1
- Criticality Benchmark Guide for Light-Water-Reactor Fuel in Transportation and Storage Packages (NUR
- Jet Impingement in High-Energy Piping Systems (NUREG/CR-7275)
- Developing a Technical Basis for Embedded Digital Devices and Emerging Technologies (NUREG/CR-7273)
- User's Manual for RESRAD-OFFSITE Code Version 4 (NUREG/CR-7268)
- Review of Radiation-Induced Concrete Degradation and Potential Implications for Structures Exposed t
- Review of Accident Tolerant Fuel Concepts with Implications to Severe Accident Progression and Radio
- Phenomena Identification Ranking Tables for Accident Tolerant Fuel Designs Applicable to Severe Acci
- Radiation Evaluation Methodology for Concrete Structures (NUREG/CR-7281 ORNL/SPR-2020/1572)
- Technical Basis for the use of Probabilistic Fracture Mechanics in Regulatory Applications: Final (N
- Regional Tectonics and Seismicity of Southwestern Iowa: Final Report: 1978-1982 (NUREG/CR-3021)
- Nonradiological Health Consequences from Evacuation and Relocation (NUREG/CR-7285)
- The Price-Anderson Act: 2021 Report to Congress, Public Liability Insurance and Indemnity Requiremen
- Exploring Advanced Computational Tools and Techniques with Artificial Intelligence and Machine Learn
- Research to Develop Flood Barrier Testing Strategies for Nuclear Power Plants (NUREG/CR-7279, INL/EX
- Multi-Mechanism Flood Hazard Assessment: Critical Review of Current Practice and Approaches and Exam
- Technical Bases for Consequence Analyses Using MACCS (MELCOR Accident Consequence Code System) (NURE
- Fuel Qualification for Molten Salt Reactors (NUREG/CR-7299, ORNL/TM-2022/2754)
- State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analysis of the Unmitigated Short
- Ultrasonic Modeling and Simulation for Nuclear Nondestructive Evaluation (NUREG/CR-7301, PNNL-33732)
- SCALE 6.2 Lattice Physics Performance Assessment (NUREG/CR-7284, ORNL/TM-2017/278)
- Baseline Risk Index for Initiating Events (BRIIE) (NUREG/CR-6932, INL/EXT-06-11950)
- Primary Water Stress Corrosion Cracking of High-Chromium Nickel-Base Welds – 2018 (NUREG/CR-7276)
- Convection-Permitting Modeling for Intense Precipitation Processes (NUREG/CR-7290)
- Updated Recommendations Related to Spent Fuel Transport and Dry Storage Shielding Analyses (NUREG/CR
- Numerical Modeling of Local Intense Precipitation Processes (NUREG/CR-7287)
- Metal Fuel Qualification: Fuel Assessment Using NRC NUREG-2246, "Fuel Qualification for Advanced Rea
- Radiation Accident Dose and Simulated Loss-of-Coolant Accident Test of Low Voltage Cables (NUREG/CR-
- Geochemical Studies of Commercial Low-Level Radioactive Waste Disposal Sites - Topical Report (NUREG
- Validating Actinides and Fission Products for Burnup Credit Criticality Safety Analyses - Nuclide Co
- Evaluating Flaw Detectability Under Limited-Coverage Conditions (NUREG/CR-7304, PNNL-34367)
- A Methodology for Allocating Nuclear Power Plant Control Nuclear to Human or Automatic Control (NURE
- Fuel Assembly and Irradiation Parametric Study for Extended-Enrichment and High-Burnup Light-Water R
- Phenomena Identification and Ranking Tables on High Burnup Fuel Fragmentation, Relocation, Dispersal
- Default Parameter Values and Distribution in RESRAD-ONSITE V7.2, RESRAD-BUILD V3.5, and RESRAD-OFFSI
- Integrated System Validation: Methodology and Review Criteria (NUREG/CR-6393, BNL-NUREG-52483)
- Validation Studies for High Burnup and Extended Enrichment Fuels in Burnup Credit Criticality Safety
- Sensitivity/Uncertainty Methods for Nuclear Criticality Safety Validation (NUREG/CR-7308, ORNL/TM-20
- Determination of Bias and Bias Uncertainty for Criticality Safety Computational Methods (NUREG/CR-73
- Publications Resulting from International Agreements
- Publications Available in Adams
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