Spotlight
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
- Glossary
- Aleatory
- Axial crack
- Base metal
- Butt weld
- Call
- Circumferential crack
- Configuration management
- Crack coalescence
- Crack growth
- Crack initiation
- Critical ratio
- Epistemic
- Fatigue
- Fracture mechanics
- Full-Text Glossary
- Idealized surface crack
- Idealized through-wall crack
- Indicator function
- Leak before break
- Limit load
- Model
- Module
- Piping
- Primary water stress-corrosion cracking (PWSCC)
- Probability distribution
- Realization
- Rupture
- Stress-intensity factor
- Surface crack
- Through-wall crack
- Transitioning crack
- Uncertainty
- Licensing Support Network (LSN) Library
- National Environmental Policy Act (NEPA)
- Refueling
- Refueling BWR
- Refueling PWR
- Drop-In Meetings
- The Student Corner
- What Is Nuclear Energy?
- Overview
- NRC Facts
- For Educators
- Science 101
- Social Media
- Multimedia
- Find a Map
- Careers
- Resources
- NRC eLearning
- History 101
- CRUD: Another Acronym Bites the Dust
- Defense in Depth - A War for Safety
- Penn State University's Breazeale Reactor Celebrates 65+ Years
- Melting Ice with the Peaceful Atom: The NRC and the End of the Cold War
- The Mystery of the Atomic Energy Commission Trowel — Part I
- The Mystery of the Trowel – Solved
- Radium Part I: Opening Pandora's Box
- Radium Part II: Trying to Close Pandora's Box
- The Reactor Safety Study: The Birth, Death and Rebirth of PRA
- Putting the Axe to the 'Scram' Myth
- The First Temple of the Atom: The AEC and the North Carolina State Research Reactor
- Ensuring Safety in the First Temple of the Atom
- "Too Cheap to Meter": A History of the Phrase
- Floating Nuclear Power Plants: A Technical Solution to a Land-based Problem (Part I)
- • Waves of Uncertainty: The Demise of the Floating Reactor Concept
- Standard Review Plans and Review Standards
- Newsletters and Other NRC Information
- Glossary
- 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
- Recently Released Documents
- Commission Papers (SECY)
- Staff Requirements Memoranda (SRMs)
- Commission Voting Records (CVR)
- Commission Action Memoranda (COMs and COMSECYs)
- Commission Meetings, Agendas, Slides, Transcripts, Meeting SRMs, and Full Written Explanation for Closed Meetings
- 2025
- 2024
- 2023
- 2022
- 2021
- Discussion of NRC's Regulatory Framework for Dry Cask Storage and Transportation of Spent Nuclear Fu
- Briefing on Advanced Reactor Preparedness Through Regulatory Engagement and Research Cooperation
- Transformation at the NRC - Midyear Review
- Briefing on 10 CFR Part 53 Licensing and Regulation of Advanced Nuclear Reactors
- 1977
- Commission Orders
- Speeches
- Commission Responses to GAO Reports
- Commission Policy Statements
- Combined Index
- Congressional Documents
- Electronic Government (E-Gov) Documents
- Enforcement Documents
- Enforcement Petition (2.206)
- Events, Reports Associated with
- Fact Sheets & Brochures
- Backgrounder on Allegations
- Backgrounder on Blending of Low-Level Radioactive Waste
- Backgrounder on Chernobyl Nuclear Power Plant Accident
- Backgrounder on Commercial Irradiators
- Backgrounder on Dirty Bombs
- Backgrounder on Effects of Electric Utility Deregulation
- Backgrounder on Fire Protection for Nuclear Power Plants
- Backgrounder on Force-on-Force Security Inspections
- Backgrounder on Improvements Resulting From Davis-Besse Incident
- Backgrounder on Incident Response
- Backgrounder on Irradiated Gemstones
- Backgrounder on Mixed Oxide Fuel
- Backgrounder on Nuclear Power Plant Licensing Process
- Backgrounder on Oversight of Nuclear Power Plants
- Backgrounder on Plutonium
- Backgrounder on Probabilistic Risk Assessment
- Backgrounder on Reactor License Renewal
- Backgrounder on Reactor License Transfers
- Backgrounder on Reactor Operator Licensing
- Backgrounder on Reactor Pressure Vessel Issues
- Backgrounder on Seismic Reviews at U.S. Nuclear Power Plants
- Backgrounder on Steam Generator Tube Issues
- Backgrounder on Underground Pipes at Nuclear Reactors
- Backgrounder on Uranium Mill Tailings
- Backgrounder on Risks Associated with Medical Events
- Backgrounder on Analysis of Cancer Risks in Populations Near Nuclear Facilities
- Backgrounder on Cyber Security
- Backgrounder on the Three Mile Island Accident
- Backgrounder on Byproduct Materials
- Backgrounder on Decommissioning Nuclear Power Plants
- Backgrounder on Dry Cask Storage of Spent Nuclear Fuel
- Backgrounder on Emergency Planning and Preparedness for Nuclear Fuel Facilities
- Backgrounder on Uranium Enrichment
- Backgrounder on Environmental Monitoring at Nuclear Power Plants
- Backgrounder on Improved Plant Safety Performance
- Backgrounder on Tritium EXIT Signs
- Backgrounder on Medical Use of Radioactive Materials
- Backgrounder on New Nuclear Plant Designs
- Backgrounder on Polonium-210
- Backgrounder on Power Uprates for Nuclear Plants
- Backgrounder on Protection and Security of Radiation Sources
- Backgrounder on Radioactive Waste
- Backgrounder on Nuclear Reactor Risk
- Backgrounder on Research and Test Reactors
- Backgrounder on Nuclear Security
- Backgrounder on Storage of Spent Nuclear Fuel
- Backgrounder on Transportation of Spent Fuel and Radioactive Materials
- Backgrounder on Tritium, Radiation Protection Limits, and Drinking Water Standards
- Backgrounder on Agreement States
- Backgrounder on Uranium Import Ban
- Drones and Nuclear Power Plant Security
- Negative Ion Products Containing Radioactive Material
- Federal Register Notices (NRC)
- Forms (NRC)
- NRC Form 529 - Dispute of Fees-for-Service Charges in Accordance with Title 10 of the Code of Federa
- NRC Form 755 – Advance Notification to the NRC of Shipments of Category 1 Quantities of Radioactive
- NRC Form 507 - Identity Verification and/or Third-Party Authorization For Freedom of Information Ac
- NRC Form 509 - Statement of Estimated Fees for Freedom of Information Act (FOIA) Request
- NRC Form 754 – Armed Security Personnel Firearms Background Check
- 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
- Spent Fuel Storage and Transportation Interim Staff Guidance
- Interim Staff Guidance Associated with Combined License (COL), Design Certification (DC), and Early
- Interim Staff Guidance Associated with Digital Instrumentation & Controls
- Interim Staff Guidance Associated with Emergency Planning for Nuclear Power Plants
- Interim Staff Guidance Used by the Division of Fuel Cycle Safety, Safeguards, and Environmental Revi
- Interim Staff Guidance for High-Level Waste Repository Safety
- License Renewal (LR) and Subsequent License Renewal (SLR) Interim Staff Guidance (ISG)
- Interim Staff Guidance Associated with Research and Test Reactors
- Interim Staff Guidance Associated with License Applications
- 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
- Confirmatory Thermal-Hydraulic Analysis To Support Specific Success Criteria in the Standardized Pla
- Confirmatory Thermal-Hydraulic Analysis To Support Specific Success Criteria in the Standardized Pla
- 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)
- Weapons Safety Assessment – Template Instructions: Chapters 1 and 2 (NUREG-2264, Volume 1)
- Weapons Safety Assessment – Template: Chapters 3 and 4 (NUREG-2264, Volume 2)
- Weapons Safety Assessment – Review Criteria: Chapters 5 and 6 (NUREG-2264, Volume 3)
- Weapons Safety Assessment – Sample Template: Chapters 7 to 9 and Appendix A (NUREG-2264, Volume 4)
- 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
- Modeling Potential Reactor Accident Consequences, State-of-the-Art Reactor Consequence Analyses: Usi
- Radioactive Waste: Production, Storage, Disposal (NUREG/BR-0216, Revision 2)
- NRC Safeguards Information Program: Helpful Resources for Applicants and Preapplicants (NUREG/BR-053
- NRC Facility Security Clearance Program: Helpful Resources For Licensees, Applicants, And Other Enti
- Atomic Fission: The Breakup of the Atomic Energy Commission and the Energy Reorganization Act of 197
- 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
- Spent Fuel Storage and Transportation of Accident Tolerant Concepts: Cr-Coated Zirconium Alloy Cladd
- Publications Resulting from International Agreements
- Survey of Member Countries' Nuclear Power Plant Fire Protection Regulations by the OECD Nuclear Ener
- Simulation with RELAP5/MOD3.3 of an Integral-Effect Test on Loop-Seal Clearing in the Upper Plenum T
- Analysis with TRACE Code of PKL III Tests G1.2. Study on Heat Transfer Mechanisms in the SG in Prese
- RELAP5 and TRACE Constitutive Relations Comparison
- Evaluation for 4-Inch Cold Leg Top-Slot Break LOCA in ATLAS Facility with RELAP5 Mod3.3 Patch5
- TRACE VVER-440/V-213 Model Cross-Code Validation (NUREG/IA-0524)
- TRACE VVER-1000/V-320 Model Cross-Code Validation (NUREG/IA-0525)
- Simulation of Total Loss of Feedwater LOFT LP-FW-1 Test using RELAP5/MOD3.3 (NUREG/IA-0526)
- Analysis of Main Steam Line Break Accident for 3-Loop PWR with RELAP5/MOD3.3 Code (NUREG/IA-0527)
- Uncertainty Analysis of Main Steam Line Break Accident for Maanshan PWR with RELAP5/DAKOTA (NUREG/IA
- Analysis with TRACE Code of PKL III Tests G1.1 & G1.1a. Study on Heat Transfer Mechanisms in the SG
- RELAP5 and TRACE Simulation of Bethsy 9.1b Test with Accuracy Quantification (NUREG/IA-0531)
- Assessment of Condensation Heat Transfer Models of TRACE V5.0 Patch 5 Using PASCAL Tests (NUREG/IA-0
- Using VARSKIN for Hot Particles Ingestion Dosimetry Evaluation (NUREG/IA-0535)
- RELAP5, TRACE and APROS Model Benchmark for the IAEA SPE-4 Experiment (NUREG/IA-0533)
- Simulations of the BEAVRS PWR with SCALE and PARCS (NUREG/IA-0529)
- Assessment of TRACE5.0 Code Against ATLAS Test A5.2. Counterpart Test to LSTF (NUREG/IA-0540)
- Post-Test Analysis of PKL III Test H2.2 Run 2 (SBO) with TRACE (NUREG/IA-0545)
- RELAP5, TRACE and APROS Model Benchmark for the IAEA SPE-2 Experiment (NUREG/IA-0544)
- Assessment of TRACE V5.0 Patch 7 Using OECD-ATLAS2 B3.2 Test (NUREG/IA-0548)
- Uncertainty and Sensitivity Analysis of Hot Leg LOCA in Two-Loop PWR Using RELAP5 Version 3.3lj (NUR
- New Functionality of TRACE: The 3DPost-Processing for the VESSEL Component in SALOME Platform (NUREG
- Maanshan PWR FLEX Program Enhance with RELAP5/MOD 3.3 (NUREG/IA-0549)
- Assessment of a PWR Control Rod Drop Transient with 3D Neutronic-Thermalhydraulic Coupled Codes RELA
- Modelling Guidelines for CCFL Representation During IBLOCA Scenarios of PWR Reactors (NUREG/IA-0550)
- Study on the Effect of Dissolved Air During Hydroaccumulator Injection (NUREG/IA-0553)
- TRACE simulations of LOCAs Together with the Complete Loss of One Emergency Core Cooling Function in
- Kuosheng BWR Decommissioning SBO Analysis with RELAP5/MOD 3.3 (NUREG/IA-0555)
- Assessments of 3D Components in System Codes Against Separate Effect Tests (NUREG/IA-0551)
- Analysis of CRDM Nozzle Break at the ATLAS Facility with 3D Components in MARS-KS and TRACE (NUREG/I
- TRACE/RELAP5 Calculation of NPP Krško SGTR Accident Under Realistic and SRP Conditions (NUREG/IA-055
- Multi-Scale Coupling of Trace and TrioCFD with the Interface for CodeCoupling (ICoCo) (NUREG/IA-0542
- TRACE Nodalization Performance in PSB-VVER SB-LOCA Benchmark (NUREG/IA-0557)
- Publications Available in Adams
- Publications Prepared by NRC Staff
- Personal Identity Verification
- Previous Site Additions
- Public Dashboards
- Regulations (NRC, 10 CFR)
- Regulatory Guides (by Division)
- Division 1 - Power Reactors
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- Division 10 - General
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- FOIA & Privacy Act
- FOIA Guide
- Amendments to the FOIA "OPEN Government Act of 2007"
- Open Government Assessment of the NRC's FOIA Process
- NRC FOIA Backlog Reduction Goals for FY2008, FY2009, and FY2010
- Privacy Act Request Guide
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- Closed Appeal & FOIA/PA Cases by Subject – FY 2025
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- Closed Appeal & FOIA/PA Cases by Subject – FY 2023
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- Recent FOIA Requests
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Page Last Reviewed/Updated Thursday, July 24, 2025
Page Last Reviewed/Updated Thursday, July 24, 2025