U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
Label
U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
Name
U.S. Nuclear Regulatory Commission
Subordinate unit
Office of Nuclear Regulatory Research
Actions
Incoming Resources
- Knowledge base report on emergency core cooling sump performance in operating light water reactors, prepared by K. Natesan [and three others]
- A formalized approach for the collection of HRA data from nuclear power plant simulators, prepared by B. Hallbert [and four others]
- GSI-191 PWR sump screen blockage chemical effects tests, thermodynamic simulations, prepared by J. McMurry ... [and others]
- Guidance on the treatment of uncertainties associated with PRAs in risk-informed decision making, draft report for comment, prepared by M. Drouin ... [and others]
- Investigations of the VVER-1000 Coolant Transient Benchmark Phase 1 with the coupled code system RELAP5/PARCS, prepared vy V. Sanchez-Espinoza
- International HRA empirical study--phase 1 report, description of overall approach and pilot phase results from comparing HRA methods to similar performance data, prepared by E. Lois ... [and others}
- Degradation of LWR core internal materials due to neutron irradiation, prepared by O.K. Chopra
- Simulation of the F2.1 experiment at PKL facility using RELAP5/MOD3, prepared by, S. Carlos ... [and others]
- Materials aging issues and aging management for extended storage and transportation of spent nuclear fuel, prepared by R.L. Sindelar ... [and others]
- Systems analysis programs for hands-on integrated reliability evaluations (SAPHIRE), version 8, prepared by C.L. Smith, S.T. Wood
- Application of surface complexation modeling to selected radionuclides and aquifer sediments, prepared by J.A. Davis
- Assessment of analysis methods for seismic shear wall capacity using JNES/NUPEC multi-axial cyclic and shaking table test data, prepared by J. Xu ... [and others]
- Non-destructive and failure evaluation of tubing from a retired steam generator, prepared by D.S. Kupperman ... [and others]
- Electric raceway fire barrier systems in U.S. nuclear power plants, draft report for comment, prepared by G. Taylor and M.H. Salley
- Design practices for communications and workstations in highly integrated control rooms, prepared by R. Kisner ... [and others]
- Reactor trip analysis at Krško Nuclear Power Plant, prepared by A. Pros̆ek, B. Mavko
- Rod bundle heat transfer test facility test plan and design, prepared by L.E. Hochreiter ... [and others] ; K. Tien, NRC project manager
- Analysis of experimental data for high-burnup PWR spent fuel isotopic validation, Vandellós II reactor, prepared by G. Ilas and I.C. Gauld
- Fire protection and fire research knowledge management digest, Office of Nuclear Regulatory Research
- Proceedings of the workshop on engineered barrier performance related to low-level radioactice waste, decommissioning, and uranium mill tailings facilities, held at the U.S. Nuclear Regulatory Commission headquarters, Rockville, MD, August 3-5, 2010, prepared by T.J. Nicholson and H.D. Arit
- Improvement of RELAP5/MOD3.3 reflood model based on the assessments against FLECHT-SEASET tests, prepared by Tong-Soo Choi ... [and others]
- Assessment of TRACE 5.0 against ROSA test 6-2, vessel lower plenum SBLOCA, prepared by S. Gallardo, V. Abella, G. Verdú
- Confirmatory thermal-hydraulic analysis to support specific success criteria in the standardized plant analysis risk models, Surry and Peach Bottom, prepared by H. Esmaili ... [et al]
- Human-performance issues related to the design and operation of small modular reactors, prepared by John O'Hara, Jim Higgins, and Michael Pena ; prepare for : Division of Risk Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Guidance on the treatment of uncertainties associated with PRAs in risk-informed decision making, draft report for comment, prepared by M. Drouin [and six others]
- Synthesis of distributions representing important non-site-specific parameters in off-site consequence analyses, prepared by N.E. Bixler, E. Clauss, and C.W. Morrow
- Fitness for duty in the nuclear industry, an update of technical issues on drugs of abuse testing and fatigue management, prepared by Kristi Branch and Kathryn Baker
- New source term model for the RESRAD-OFFSITE code version 3, prepared by C. Yu [and three others]
- Effect of LWR coolant environments on the fatigue life of reactor materials, final report, prepared by O.K. Chopra and W.J. Shack
- Risk-informed assessment of degraded containment vessels, prepared by B.W. Spencer, J.P. Petti, D.M. Kunsman
- In-tube steam condensation in the presence of air under transient conditions, prepared by A. Tanrikut, O. Yesin
- Assessment of noise level for eddy current inspection of steam generator tubes, prepared by S. Bakhtari, D.S. Kupperman, and W.J. Shack
- Instrumentation and controls in nuclear power plants, an emerging technologies update, K. Korsah, ... [and others]
- Essential elements of an electric cable condition monitoring program, prepared by M. Villaran and R. Lofaro
- Material property correlations, comparisons between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO, prepared by W.G. Luscher and K.J. Geelhood
- A large scale validation of a methodology for assessing software reliability, prepared by C.S. Smidts ... [et al]
- FRAPCON-3.4, a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup, prepared by K.J. Geelhood, W.G. Luscher, C. E. Beyer
- Early leak detection external to structures at nuclear power plants, prepared by Mark Fuhrmann and Joseph Kanney
- Experimental studies of reinforced concrete structures under multidirectional earthquakes and design implications, prepared by N. Simos and C.H. Hofmayer
- PRA procedures guide, a guide to the performance of probabilistic risk assessments for nuclear power plants, prepared under the auspices of the American Nuclear Society, the Institute of Electrical and Electronics Engineers
- Expert panel report on proactive materials degradation assessment, prepared by P.L. Andresen ... [and others]
- Predictive bias and sensitivity in NRC fuel performance codes, prepared by K.J. Geelhood .... [and others]. ; Pacific Northwest National Laboratory
- Estimation of operator action time windows by RELAP/MOD3.3, A. Prošek, B. Mavko, M. Čepin
- Final report - evaluation of chemical effects phenomena in post-LOCA coolant, prepared by C.H. Delegard ... [and others]
- A compilation of elevated temperature concrete material property data and information for use in assessments of nuclear power plant reinforced concrete structures, prepared by D.J. Naus
- Verification of RESRAD-OFFSITE, prepared by C. Yu ... [and others]
- Simulation of PKL loss of RHRS experiment F2 ... 2 run 2 with RELAP5 and TRACE codes, application to a PWR NPP model, prepared by César Queral, Antonio Expósito, and Alberto Concejal
- Validation of SCALE for high temperature gas-cooled reactor analysis, prepared by Germina Ilas ... [and others]
- Stress corrosion cracking in nickel-base alloys 690 and 152 weld in simulated PWR environment - 2009, prepared by B. Alexandeanu
- State-of-the-art-reactor consequence analyses (SOARCA) report, prepared by Richard Chang [and five others]
- Qualification of continuous duty safety-related motors for nuclear power plants
- Regulatory guide 1.192, operation and maintenance code case acceptability, ASME OM code
- Nuclear criticality safety standards for fuels and material facilities
- Regulatory Guide 1.203, transient and accident analysis methods
- Regulatory guide 1.197, demonstrating control room envelope integrity at nuclear power reactors
- Draft Regulatory Guide DG-1149, qualification of safety-related motor control centers for nuclear power plants
- Draft regulatory guide DG-1132, qualification of safety-related cables and field splices for nuclear power plants
- Regulatory guide 1.170, software test documentation for digital computer software used in safety systems of nuclear power plants
- Regulatory guide 1.68, initial test programs for water-cooled nuclear power plants
- Methods for measuring effective dose equivalent from external exposure
- Instrument sensing lines
- Guidance for the assessment of beyond-design-basis aircraft impacts
- Three Mile Island accident of 1979 knowledge management digest
- Regulatory Guide 1.200, an approach for determining the technical adequacy of probabilistic risk assessment results for risk-informed activities
- Draft regulatory guide DG-1178, instrument sensing lines
- Regulatory guide 1.182, assessing and managing risk before maintenance activities at nuclear power plants
- Regulatory guide 1.183, alternative radiological source terms for evaluating design basis accidents at nuclear power reactors
- Regulatory guide 1.184, decommissioning of nuclear power reactors
- Regulatory guide 1.179, standard format and content of license termination plans for nuclear power reactors
- Regulatory guide 1.172, software requirements specifications for digital computer software used in safety systems of nuclear power plants
- Cyber security programs for nuclear facilities
- An approach for plant-specific, risk-informed decisionmaking, technical specifications
- Regulatory Guide 1.205, risk-informed, performance-based fire protection for existing light-water nuclear power plants
- Draft Regulatory Guide DG-1203, containment performance for pressure loads
- Draft regulatory guide DG-1186, measuring, evaluating, and reporting radioactive material in liquid and gaseous effluents and solid waste
- Draft regulatory guide DG-1189, an acceptable model and related statistical methods for the analysis of fuel densification
- Draft regulatory guide DG-1142, guidelines for environmental qualification of safety-related computer-based instrumentation and control systems in nuclear power plants
- Regulatory guide 1.180, guidelines for evaluating electromagnetic and radio-frequency interference in safety-related instrumentation and control systems
- Qualification of safety-related motor control centers for nuclear power plants
- Control of the processing and use of stainless steel
- Protection of safeguards information
- Draft regulatory guide DG-1195, availability of electric power sources
- Regulatory guide 1.198, procedures and criteria for assessing seismic soil liquefaction at nuclear power plant sites
- Draft regulatory guide DG-1144, guidelines for evaluating fatigue analyses incorporating the life reduction of metal components due to the effects of the light-water reactor environment for new reactors
- Qualification of safety-related cables and field splices for nuclear power plants
- Inservice inspection code case acceptability, ASME section XI, division 1
- Standard format and content for emergency plans for fuel cycle and materials facilities
- Regulatory guide 1.196, control room habitability at light-water nuclear power reactors
- Draft regulatory guide DG-1175, seismic qualification of electric and active mechanical equipment and functional qualification of active mechanical equipment for nuclear power plants
- Regulatory guide 1.194, atmospheric relative concentrations for control room radiological habitability assessments at nuclear power plants
- Training and qualification of security personnel at nuclear power reactor facilities
- Qualification for cement grouting for prestressing tendons in containment structures
- Regulatory Guide 1.207, guidelines for evaluating fatigue analyses incorporating the life reduction of metal components due to the effects of the light-water reactor environment for new reactors
- Regulatory Guide 1.209, guidelines for environmental qualification of safety-related computer-based instrumentation and control systems in nuclear power plants
- Regulatory guide 1.186, guidance and examples for identifying 10 CFR 50.2 design bases
- Planned special exposure
- Control of preheat temperature for welding of low-alloy steel
- Information relevant to ensuring that radiation exposures at medical institutions will be as low as is reasonably achievable
- An approach for using probabilistic risk-assessment in risk-informed decisions on plant-specific changes to the licensing basis
- Regulatory guide 1.191, fire protection program for nuclear power plants during decommissioning and permanent shutdown
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- Qualification of continuous duty safety-related motors for nuclear power plants
- Nuclear criticality safety standards for fuels and material facilities
- Methods for measuring effective dose equivalent from external exposure
- Instrument sensing lines
- Guidance for the assessment of beyond-design-basis aircraft impacts
- Three Mile Island accident of 1979 knowledge management digest
- Cyber security programs for nuclear facilities
- An approach for plant-specific, risk-informed decisionmaking, technical specifications
- Qualification of safety-related motor control centers for nuclear power plants
- Control of the processing and use of stainless steel
- Protection of safeguards information
- Qualification of safety-related cables and field splices for nuclear power plants
- Inservice inspection code case acceptability, ASME section XI, division 1
- Standard format and content for emergency plans for fuel cycle and materials facilities
- Training and qualification of security personnel at nuclear power reactor facilities
- Qualification for cement grouting for prestressing tendons in containment structures
- Planned special exposure
- Control of preheat temperature for welding of low-alloy steel
- Information relevant to ensuring that radiation exposures at medical institutions will be as low as is reasonably achievable
- An approach for using probabilistic risk-assessment in risk-informed decisions on plant-specific changes to the licensing basis
- Physical models for design and operation of hydraulic structures and systems for nuclear power plants
- Control of stainless steel weld cladding of low-alloy steel components
- Fire protection for nuclear power plants
- Guide for the preparation of applications for medical use programs
- Initial startup test program to demonstrate remote shutdown capability for water-cooled nuclear power plants
- Administrative practices in radiation surveys and monitoring
- Design, construction, and inspection of embankment retention systems at uranium recovery facilities
- Materials and inspections for reactor vessel closure studs
- Containment isolation provisions for fluid systems
- ASME code cases not approved for use
- Criteria for use of computers in safety systems of nuclear power plants
- Standard format and content of license termination plans for nuclear power reactors
- Guidance to operators at the controls and to senior operators in the control room of a nuclear power unit
- Control of electroslag weld properties
- Manual initiation of protective actions
- Service level I, II, and III protective coatings applied to nuclear power plants
- General fire protection guide for plutonium processing and fuel fabrication plants
- Guidance for ITAAC closure under 10 CFR part 52
- Design, construction, and inspection of embankment retention systems at fuel cycle facilities
- Nuclear power plant simulation facilities for use in operator training, license examinations, and applicant experience requirements
- Concrete shields and generic shield testing for nuclear power plants
- Preparation of an environmental report to support a rulemaking petition seeking an exemption for a radionuclide-containing product
- Sizing of large lead-acid storage batteries
- Standard format and content for the health and safety sections of license renewal applications for uranium processing and fuel fabrication
- Bypassed and inoperable status indication for nuclear power plant safety systems
- Pressure-sensitive and tamper-indicating device seals for material control and accounting of special nuclear material
- Establishing quality assurance programs for the manufacture and distribution of sealed sources and devices containing byproduct material
- Qualification of continuous duty safety-related motors for nuclear power plants
- Knowledge base report on emergency core cooling sump performance in operating light water reactors, prepared by K. Natesan [and three others]
- A formalized approach for the collection of HRA data from nuclear power plant simulators, prepared by B. Hallbert [and four others]
- Nuclear criticality safety standards for fuels and material facilities
- Human-performance issues related to the design and operation of small modular reactors, prepared by John O'Hara, Jim Higgins, and Michael Pena ; prepare for : Division of Risk Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Methods for measuring effective dose equivalent from external exposure
- Guidance on the treatment of uncertainties associated with PRAs in risk-informed decision making, draft report for comment, prepared by M. Drouin [and six others]
- Instrument sensing lines
- Guidance for the assessment of beyond-design-basis aircraft impacts
- Synthesis of distributions representing important non-site-specific parameters in off-site consequence analyses, prepared by N.E. Bixler, E. Clauss, and C.W. Morrow
- Fitness for duty in the nuclear industry, an update of technical issues on drugs of abuse testing and fatigue management, prepared by Kristi Branch and Kathryn Baker
- New source term model for the RESRAD-OFFSITE code version 3, prepared by C. Yu [and three others]
- Cyber security programs for nuclear facilities
- An approach for plant-specific, risk-informed decisionmaking, technical specifications
- Early leak detection external to structures at nuclear power plants, prepared by Mark Fuhrmann and Joseph Kanney
- Experimental studies of reinforced concrete structures under multidirectional earthquakes and design implications, prepared by N. Simos and C.H. Hofmayer
- State-of-the-art-reactor consequence analyses (SOARCA) report, prepared by Richard Chang [and five others]
- Computational fluid dynamics best practice guidelines for dry cask applications, draft report for comment, prepared by Ghani Zigh and Jorge Solis
- Qualification of safety-related motor control centers for nuclear power plants
- Control of the processing and use of stainless steel
- Protection of safeguards information
- The technical basis supporting ASME code, section XI, appendix VIII, performance demonstration for ultrasonic examination, prepared by S.R. Doctor [and three others]
- Compensatory and Alternative Regulatory MEasures for Nuclear power plant FIRE protection (CARMEN-FIRE), draft report for comment, prepared by K. Sullivan
- A review of the effects of radiation on microstructure and properties of concretes used in nuclear power plants, prepared by Kaspar William, Yunping Xi, Dan Naus
- Assessing the potential for biorestoration of uranium in situ recovery sites, prepared by S.B. Yabusaki [and six others]
- MACCS best practices as applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project, prepared by Nathan Bixler [and three others]
- Computational benchmark for estimation of reactivity margin from fission products and minor actinides in BWR burnup credit, prepared by D.E. Mueller [and three others] ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Joint _assessment of _cable damage and _quantification of _effects from f_i_r_e (JACQUE-FIRE), final report
- Cable heat release, ignition, and spread in tray installations during fire (CHRISTIFIRE), phase 1, horizontal trays, prepared by K. McGrattan [and five others]
- Qualification of safety-related cables and field splices for nuclear power plants
- Inservice inspection code case acceptability, ASME section XI, division 1
- Standard format and content for emergency plans for fuel cycle and materials facilities
- IJS procedure for converting input deck from RELAP5 to TRACE, prepared by: A. Prošek, O.A. Berar, B. Mavko
- Application of TRACE V5.0 P2 to China domestic PWR LBLOCA analysis, prepared by: Feng Jinjun [and three others]
- Electrical cable test results and analysis during fire exposure (ELECTRA-FIRE), a consolidation of three major fire-induced circuit and cable failure experiments performed between 2001 and 2011 ; final report, prepared by: G. Taylor [and five others]
- Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES)-2010
- Ultrasonic phased array assessment of the interference fit and leak path of the North Anna Unit 2 control rod drive mechanism nozzle 63 with destructive validation, prepared by S. L. Crawford [and four others]
- Training and qualification of security personnel at nuclear power reactor facilities
- Computational fluid dynamics best practice guidelines for dry cask applications, final report, prepared by Ghani Zigh and Jorge Solis
- Qualification for cement grouting for prestressing tendons in containment structures
- Characterization of thermal-hydraulic and ignition phenomena in prototypic, full-length boiling water reactor spent fuel pool assemblies after a postulated complete loss-of-coolant accident, prepared by E.R. Lindgren and S.G. Durbin ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- VARSKIN 5, a computer code for skin contamination dosimetry, prepared by D.M. Hamby [and three others]
- Planned special exposure
- Control of preheat temperature for welding of low-alloy steel
- Information relevant to ensuring that radiation exposures at medical institutions will be as low as is reasonably achievable
- An approach for using probabilistic risk-assessment in risk-informed decisions on plant-specific changes to the licensing basis
- Weld residual stress finite element analysis validation, prepared by Michael Benson, David Rudland, and Aladar Csontos
- Nuclear power plant fire modeling analysis guidelines (NPP FIRE MAG), final report
- Physical models for design and operation of hydraulic structures and systems for nuclear power plants
- Control of stainless steel weld cladding of low-alloy steel components
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