U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
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Featured books
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- MFMethods for Applying Risk Analy...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES)-2010
no cover - TMThree Mile Island accident of 1...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Three Mile Island accident of 1979 knowledge management digest
no cover - NPNuclear power plant fire modeli...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Nuclear power plant fire modeling application guide
no cover - NPNuclear power plant fire modeli...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Nuclear power plant fire modeling application guide
no cover - EFEPRI/NRC-RES fire PRA methodolo...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
EPRI/NRC-RES fire PRA methodology for nuclear power facilities
no cover - HIHuman interaction with reused soilU.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Human interaction with reused soil
no cover - SOStudy of the effect of integral...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Study of the effect of integral burnable absorbers for PWR burnup credit
no cover - AOAssessment of risk significance...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Assessment of risk significance associated with issues identified at D.C. Cook Nuclear Power Plant
no cover - DRDraft regulatory guide DG-1093U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Draft regulatory guide DG-1093
no cover - AOAssessment of a reactor coolant...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Assessment of a reactor coolant pump trip for TRILLO NPP with RELAP5/MOD3.2
no cover - DRDraft regulatory guide DG-1104U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Draft regulatory guide DG-1104
no cover - CNConfrentes NPP (BWR/6) ATWS (MS...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Confrentes NPP (BWR/6) ATWS (MSIVC) analysis with TRAC-BF1
no cover - DRDraft regulatory guide DG-1095U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Draft regulatory guide DG-1095
no cover - RARegulatory analysis guidelines...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Regulatory analysis guidelines of the U.S. Nuclear Regulatory Commission
no cover - DRDraft regulatory guide DG-9001U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Draft regulatory guide DG-9001
no cover - DRDraft regulatory guide DG-3014U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Draft regulatory guide DG-3014
no cover - MOModification of USNRC's FRAP-T6...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Modification of USNRC's FRAP-T6 fuel rod transient code for high burnup VVER fuel
no cover - DRDraft regulatory guide DG-1086U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Draft regulatory guide DG-1086
no cover - DRDraft regulatory guide DG-1081U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Draft regulatory guide DG-1081
no cover - EOElements of an approach to perf...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Elements of an approach to performance-based regulatory oversight
no cover - DBData base on the behavior of hi...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Data base on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity accident conditions
no cover - AOAssessment of RELAP5/MOD3.2 for...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Assessment of RELAP5/MOD3.2 for steam condensation experiments in the presence of noncondensibles in a vertical tube of PCCS
no cover - AOAssessment of RELAP5/MOD3.2 usi...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6
no cover - AOAssessment of RELAP5/MOD3.1 usi...U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Assessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01
no cover
Works in catalog
Quick navigation into the work-level grouping pages behind the featured books.
- Open Work
Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES)-2010
- Open Work
Three Mile Island accident of 1979 knowledge management digest
- Open Work
Nuclear power plant fire modeling application guide
- Open Work
Nuclear power plant fire modeling application guide
- Open Work
EPRI/NRC-RES fire PRA methodology for nuclear power facilities
- Open Work
Human interaction with reused soil
- Open Work
Study of the effect of integral burnable absorbers for PWR burnup credit
- Open Work
Assessment of risk significance associated with issues identified at D.C. Cook Nuclear Power Plant
- Open Work
Draft regulatory guide DG-1093
- Open Work
Assessment of a reactor coolant pump trip for TRILLO NPP with RELAP5/MOD3.2
- Open Work
Draft regulatory guide DG-1104
- Open Work
Confrentes NPP (BWR/6) ATWS (MSIVC) analysis with TRAC-BF1
- Open Work
Draft regulatory guide DG-1095
- Open Work
Regulatory analysis guidelines of the U.S. Nuclear Regulatory Commission
- Open Work
Draft regulatory guide DG-9001
- Open Work
Draft regulatory guide DG-3014
- Open Work
Modification of USNRC's FRAP-T6 fuel rod transient code for high burnup VVER fuel
- Open Work
Draft regulatory guide DG-1086
- Open Work
Draft regulatory guide DG-1081
- Open Work
Elements of an approach to performance-based regulatory oversight
- Open Work
Data base on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity accident conditions
- Open Work
Assessment of RELAP5/MOD3.2 for steam condensation experiments in the presence of noncondensibles in a vertical tube of PCCS
- Open Work
Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6
- Open Work
Assessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01