U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
United States Nuclear Regulatory Commission Office of Nuclear Regulatory Research
VIAF ID: 140695594 ( Corporate )
Permalink: http://viaf.org/viaf/140695594
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- 110 2 _ ‡a U.S. Nuclear Regulatory Commission. ‡b Office of Nuclear Regulatory Research
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- 110 _ _ ‡a United States ‡b Nuclear Regulatory Commission ‡b Office of Nuclear Regulatory Research
4xx's: Alternate Name Forms (18)
Works
Title | Sources |
---|---|
The Browns Ferry Nuclear Plant fire of 1975 knowledge management digest | |
CARMEN-FIRE | |
Characterization of nuclear reactor ... 1984: | |
Draft regulatory guide | |
Executive summary of safeguards ... 1977 (subdiv.) | |
Heavy-section steel technology program | |
High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation quarterly progress report | |
International agreement report | |
Materials and design bases issues ... [MI] 1993: | |
Mechanical fatigue testing of high-burnup fuel for transportation applications | |
Natural circulation (interruption) analysis with MELCOR 2.2 during asymmetric cooldown transients | |
NRC safety research in support of regulation. | |
Nuclear power plant fire ignition frequency and non-suppression probability estimation using the updated fire events database : United States fire event experience through 2009. | |
Nuclear Regulatory Commission reviewer aid for evaluating the human-performance aspects related to the design and operation of small modular reactors | |
Overview of nuclear data uncertainty in scale and application to light water reactor uncertainty analysis | |
Passive nondestructive assay of nuclear materials | |
Primary water stress corrosion cracking of high-chromium, nickel-base welds near dissimilar metal weld interfaces | |
Proceedings of the DOE/NRC Nuclear Air Cleaning Conference | |
Proceedings of the Radon Barriers Workshop, July 25-26, 2018, NRC Headquarters, Rockville, MD | |
Proceedings of the ... Water Reactor Safety Information Meeting | |
Proceedings of the Workshop on the Role of Natural Analogs in Geologic Disposal of High-Level Nuclear Waste : held in San Antonio TX, July 22-25, 1991 | |
Proposed validation procedure | |
Refining And Characterizing Heat Release Rates From Electrical Enclosures During Fire (RACHELLE-FIRE) : final report. | |
Regulatory approaches for addressing reprocessing facility risks : an assessment | |
Regulatory guide (U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research) | |
Reliability assessment of remote visual examination | |
Report on emergency core cooling sump performance in operating light water reactors. | |
Report to Congress on abnormal occurrences. | |
A report to Congress on nuclear regulatory research : project descriptions for FY ... | |
Research activities | |
Research news (Washington, D.C.) | |
Response of nuclear power plant instrumentation cables exposed to fire conditions | |
Results of open testing for the program to assess the reliability of emerging nondestructive techniques | |
Review guidelines for field-programmable gate arrays in nuclear power plant safety systems | |
Review of information for spent nuclear fuel burnup confirmation | |
Sector population, land fraction, and economic estimation program : user guide, model manual, and verification report | |
Seismic isolation of nuclear power plants using elastomeric bearings | |
Simulation of the G3.1 Experiment at PKL Facility Using RELAP5/Mod3.3 | |
SNAP/RADTRAD 4.0 : description of models and methods | |
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 conditions | |
SSC | |
SSC an advanced thermohydraulic transient code for LMFBRs. | |
Stability of circumferential flaws in once-through steam generator tubes under thermal loading during LOCA, MSLB, and FWLB | |
Stand. dev. | |
Standards development : status summary report : data for decisions, management by objectives. | |
State-of-the-art-reactor consequence analysis (SOARCA) project : Sequoyah integrated deterministic and uncertainty analyses | |
Statistical methods for nuclear material management | |
Status summary report, water reactor safety research | |
Stress corrosion cracking of cold worked alloy 690 | |
Study of unusual occurrence of a partial core uncovery in an SBLOCA scenario | |
Susceptibility of nuclear stations to external faults | |
Technical basis for regulatory guidance on the alternate pressurized thermal shock rule : final report | |
Technical basis for the containment protection and release reduction rulemaking for boiling water reactors with Mark I and Mark II containments | |
Technical considerations for seismic isolation of nuclear facilities | |
Temperatures and water potentials in shallow, unsaturated alluvium, Amargosa Desert | |
Testing to evaluate extended battery operation in nuclear power plants | |
Thermal analysis of horizontal storage casks for extended storage applications | |
Toward a more risk-informed and performance-based framework for the regulation of the seismic safety of nuclear power plants | |
TRACE (V 5.0 Patch 2) validation based on the RELAP5-calculation of FIX-III LOCA experiments No. 5052, 4011, 3051 | |
TRACE VVER-440/V-213 model validation | |
Transactions of the ... Nuclear Safety Research Conference. | |
Transfer factors for contaminant uptake by fruit and nut trees | |
Tsunami hazard assessment based on wave generation, propagation, and inundation modeling for the United States east coast | |
Uncertainty analysis of the unmitigated long-term station blackout of the Peach Bottom Atomic Power Station | |
Updated implementation guidelines for SSHAC hazard studies | |
Uranium sequestration during biostimulated reduction and in response to the return of oxic conditions in shallow aquifers | |
User's guide for RESRAD-OFFSITE | |
Validation of ke̳f̳f̳ calculations for extended BWR burnup credit | |
VARSKIN 5 : a computer code for skin contamination dosimetry | |
Verification and validation of selected fire models for nuclear power plant applications. | |
Weld residual stress finite element analysis validation. |