U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
VIAF ID: 140695594 (Corporate)
Permalink: http://viaf.org/viaf/140695594
Preferred Forms
4xx's: Alternate Name Forms (4)
Works
| Title | Sources |
|---|---|
| The Browns Ferry Nuclear Plant fire of 1975 knowledge management digest |
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| CARMEN-FIRE |
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| Characterization of nuclear reactor ... 1984: |
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| Draft regulatory guide |
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| Executive summary of safeguards ... 1977 (subdiv.) |
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| Fitness for duty in the nuclear power industry : an update of technical issues on drugs of abuse testing and fatigue management |
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| Formalized approach for the collection of human reliability analysis data from nuclear power plant simulators |
|
| Global seismicity and world cities |
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| Guidance on the treatment of uncertainties associated with PRAs in risk-informed decisionmaking, final report |
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| Heavy-section steel technology program |
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| High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation quarterly progress report |
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| Historical review and observations of defense-in-depth |
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| The Impact of LWR decontaminations on solidification, waste disposal and associated occupational exposure, annual report |
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| Impact of variation in environmental conditions on the thermal performance of dry storage casks : final report |
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| Influence of coupling erosion and hydrology on the long-term performance of engineered surface barriers |
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| International agreement report |
|
| Knowledge management library for the Three Mile Island unit 2 accident of 1979. |
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| Large scale earthquake simulation of a hybrid lead rubber isolation system designed with consideration of nuclear seismicity |
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| Long-range research plan |
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| Managing PWSCC in butt welds by mitigation and inspection |
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| Materials and design bases issues ... [MI] 1993: |
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| Mechanical fatigue testing of high-burnup fuel for transportation applications |
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| Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES)-2012. |
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| MILDOS-AREA computational verification : version 4 |
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| Modeling a digital feedwater control system using traditional probabilistic risk assessment methods : final report |
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| NPP FIRE MAG |
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| NRC safety research in support of regulation |
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| Nuclear power plant fire ignition frequency and non-suppression probability estimation using the updated fire events database : United States fire event experience through 2009. |
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| Nuclear power plant fire modeling application guide : draft report for comment. |
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| Nuclear Regulatory Commission reviewer aid for evaluating the human-performance aspects related to the design and operation of small modular reactors |
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| Passive nondestructive assay of nuclear materials |
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| Proceedings of the DOE/NRC Nuclear Air Cleaning Conference |
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| Proceedings of the ... Water Reactor Safety Information Meeting |
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| 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 |
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| Refining And Characterizing Heat Release Rates From Electrical Enclosures During Fire (RACHELLE-FIRE) : final report. |
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| Regulatory approaches for addressing reprocessing facility risks : an assessment |
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| Regulatory guide (U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research) |
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| Report on emergency core cooling sump performance in operating light water reactors. |
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| Report to Congress on abnormal occurrences. |
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| A report to Congress on nuclear regulatory research : project descriptions for FY ... |
|
| Research activities. |
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| Research news (Washington, D.C.) |
|
| 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 |
|
| SNAP/RADTRAD 4.0 : description of models and methods |
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| 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 |
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| SSC |
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| SSC an advanced thermohydraulic transient code for LMFBRs. |
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| Stability of circumferential flaws in once-through steam generator tubes under thermal loading during LOCA, MSLB, and FWLB |
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| Stand. dev. |
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| Standards development : status summary report : data for decisions, management by objectives. |
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| State-of-the-art-reactor consequence analyses project. |
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| Statistical methods for nuclear material management |
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| Status summary report, water reactor safety research |
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| Susceptibility of nuclear stations to external faults |
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| Temperatures and water potentials in shallow, unsaturated alluvium, Amargosa Desert |
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| Testing to evaluate extended battery operation in nuclear power plants |
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| Thermal analysis of horizontal storage casks for extended storage applications |
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| Toward a more risk-informed and performance-based framework for the regulation of the seismic safety of nuclear power plants |
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| Transactions of the ... Nuclear Safety Research Conference. |
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| Transfer factors for contaminant uptake by fruit and nut trees |
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| Tsunami hazard assessment based on wave generation, propagation, and inundation modeling for the United States east coast |
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| Uncertainty analysis of the unmitigated long-term station blackout of the Peach Bottom Atomic Power Station |
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| Uranium sequestration during biostimulated reduction and in response to the return of oxic conditions in shallow aquifers |
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| User's guide for RESRAD-OFFSITE |
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| VARSKIN 5 : a computer code for skin contamination dosimetry |
|
