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 |
![]() |
CARMEN-FIRE |
![]() |
Characterization of nuclear reactor ... 1984: |
![]() |
Draft regulatory guide |
![]() |
Executive summary of safeguards ... 1977 (subdiv.) |
![]() ![]() |
Expanded materials degradation assessment (EMDA). |
![]() |
Experimental study of embrittlement of Zr-1%Nb VVER cladding under LOCA-relevant conditions |
![]() |
Final report of NRC AP600 research conducted at Oregon State University |
![]() |
Fitness for duty in the nuclear power industry : an update of technical issues on drugs of abuse testing and fatigue management |
![]() |
Formalized approach for the collection of human reliability analysis data from nuclear power plant simulators |
![]() |
Global seismicity and world cities |
![]() |
Guidance on the treatment of uncertainties associated with PRAs in risk-informed decisionmaking, final report |
![]() |
Heavy-section steel technology program |
![]() |
High-temperature gas-cooled reactor safety studies for the Division of Accident Evaluation quarterly progress report |
![]() |
Historical review and observations of defense-in-depth |
![]() |
The Impact of LWR decontaminations on solidification, waste disposal and associated occupational exposure, annual report |
![]() |
Impact of variation in environmental conditions on the thermal performance of dry storage casks : final report |
![]() |
Influence of coupling erosion and hydrology on the long-term performance of engineered surface barriers |
![]() |
International agreement report |
![]() |
Knowledge management library for the Three Mile Island unit 2 accident of 1979. |
![]() |
Large scale earthquake simulation of a hybrid lead rubber isolation system designed with consideration of nuclear seismicity |
![]() |
Long-range research plan |
![]() |
Managing PWSCC in butt welds by mitigation and inspection |
![]() |
Materials and design bases issues ... [MI] 1993: |
![]() ![]() |
Mechanical fatigue testing of high-burnup fuel for transportation applications |
![]() |
Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES)-2012. |
![]() |
MILDOS-AREA computational verification : version 4 |
![]() |
Modeling a digital feedwater control system using traditional probabilistic risk assessment methods : final report |
![]() |
NPP FIRE MAG |
![]() |
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 power plant fire modeling application guide : draft report for comment. |
![]() |
Nuclear Regulatory Commission reviewer aid for evaluating the human-performance aspects related to the design and operation of small modular reactors |
![]() |
Passive nondestructive assay of nuclear materials |
![]() |
Proceedings of the DOE/NRC Nuclear Air Cleaning Conference |
![]() |
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 |
![]() |
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) |
![]() |
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.) |
![]() |
Review guidelines for field-programmable gate arrays in nuclear power plant safety systems |
![]() |
Review of information for spent nuclear fuel burnup confirmation |
![]() |
A review of the effects of radiation on microstructure and properties of concretes used in nuclear power plants |
![]() |
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 |
![]() |
Stand. dev. |
![]() |
Standards development : status summary report : data for decisions, management by objectives. |
![]() |
State-of-the-art-reactor consequence analyses project. |
![]() |
Statistical methods for nuclear material management |
![]() |
Status summary report, water reactor safety research |
![]() |
Susceptibility of nuclear stations to external faults |
![]() |
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 |
![]() |
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 |
![]() |
Uranium sequestration during biostimulated reduction and in response to the return of oxic conditions in shallow aquifers |
![]() |
User's guide for RESRAD-OFFSITE |
![]() |
VARSKIN 5 : a computer code for skin contamination dosimetry |
![]() |