Idaho National Engineering Laboratory
Resource Information
The organization Idaho National Engineering Laboratory represents an institution, an association, or corporate body that is associated with resources found in Indiana State Library.
The Resource
Idaho National Engineering Laboratory
Resource Information
The organization Idaho National Engineering Laboratory represents an institution, an association, or corporate body that is associated with resources found in Indiana State Library.
- Label
- Idaho National Engineering Laboratory
- Authority link
- (EG-IN)1025259
173 Items by the Organization Idaho National Engineering Laboratory
28 Items that are about the Organization Idaho National Engineering Laboratory
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Context of Idaho National Engineering LaboratoryContributor of
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- 1977 environmental monitoring program report for Idaho National Engineering Laboratory site
- A review of the Three Mile Island-1 probabilistic risk assessment
- A systematic process for developing and assessing accident management plans
- Accident management information needs
- Accident management information needs for a BWR with a MARK I containment
- Aging data analysis and risk assessment : development and demonstration study
- Aging evaluation of class 1E batteries : seismic testing
- Aging of safety class 1E transformers in safety systems of nuclear power plants
- Agribusiness geothermal energy utilization potential of Klamath and Western Snake River Basin, Oregon
- An Assessment of BWR Mark III containment challenges, failure modes, and potential improvements in performance
- An Assessment of BWR Mark-II containment challenges, failure modes, and potential improvements in performance
- An Investigation of core liquid level depression in small break loss-of-coolant accidents
- An assessment of RELAP5/MOD2 applicability to loss-of-feedwater transient analysis in a Babcock and Wilcox reactor plant
- An integrated structure and scaling methodology for severe accident technical issue resolution : draft report for comment
- An overview of BWR Mark-I containment venting risk implications : an evaluation of potential Mark-1 containment improvements
- Annual report of the TMI-2 EPICOR-II resin/liner investigation : Low-level Waste Data Base Development Program for fiscal year 1988
- Application of microwave energy to post-calcination treatment of high-level nuclear wastes
- Assessment of ISLOCA risk-methodology and application to a Babcock and Wilcox nuclear power plant
- Assessment of ISLOCA risk-methodology and application to a Combustion Engineering plant
- Assessment of ISLOCA risk-methodology and application to a Westinghouse four-loop ice condenser plant
- Assessment of the potential for high-pressure melt ejection resulting from a Surry Station blackout transient
- BWR reactor water cleanup system flexible wedge gate isolation value qualification and high energy flow interruption test
- Biodegradation testing of TMI-2 EPICOR-II waste forms
- Calcination flowsheet development
- Calculations to estimate the margin to failure in the TMI-2 vessel
- Characteristics of low-level radioactive decontamination waste
- Characteristics of low-level radioactive waste
- Characteristics of low-level radioactive waste
- Classification of transportation packaging and dry spent fuel storage system components according to importance to safety
- Common cause failure analysis techniques : a review and comparative evaluation
- Component evaluation for intersystem loss-of-coolant accidents in advanced light water reactors
- Compression and immersion tests and leaching of radionuclides, stable metals, and chelating agents from cement-solidified decontamination waste collected from nuclear power stations
- Consequences of the loss of the residual heat removal systems in pressurized water reactors
- Containment venting analysis for the Shoreham Nuclear Power Station
- Dawsonite and nahcolite survey
- Decontamination of the waste calcining facility : a historical review
- Determination of the bias in LOFT fuel peak cladding temperature data from the blowdown phase of large-break LOCA experiments
- Developing and assessing accident management plans for nuclear power plants
- Development and use of a train-level probabilistic risk assessment
- Development of a pelleted waste form for high-level ICPP zirconia wastes
- Development of the LOFT prototype drag screen : air-water testing
- EPICOR-II resin/liner investigation : low-level waste data base development program for fiscal year 1990
- Early waste retrieval final report
- Effect of feed atomization and vessel configuration on fines formation and entrainment from fluidized-bed calciners
- Effect of pH on the release of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resins collected from operating nuclear power stations
- Effectiveness and safety aspects of selected decontamination processes
- Energy conservation with fired heaters
- Environmental surveillance report for the INEL radioactive waste management complex
- Evaluation of boiling water reactor water-level sensing line break and single failure : generic issue 101 boiling water reactor level redundancy - technical findings
- Evaluation of plutonium analysis techniques for a continuous alpha monitor
- Evaluation of well-purging effects on water-quality results for samples collected from the eastern Snake River Plain aquifer underlying the Idaho National Laboratory, Idaho
- Evidence of aging effects on certain safety-related components
- Examination of relocated fuel debris adjacent to the lower head of the TMI-2 reactor vessel
- Examples, clarifications, and guidance on preparing requests for relief from pump and valve inservice testing requirements
- Fault tree, event tree, and piping & instrumentation diagram (FEP) editors, version 4.0 : reference manual
- Field lysimeter investigations : Low-Level Waste Data Base Development Program for fiscal year ...
- Field lysimeter investigations : low-level waste data base development program for fiscal year 1991 : annual report
- Field lysimeter investigations : low-level waste data base development program for fiscal year 1992 : annual report
- Field lysimeter investigations : low-level waste data base development program for fiscal year 1993 : annual report
- Field lysimeter investigations--test results
- Final report : development of a metal matrix for incorporating high-level commercial waste
- Gate valve and motor-operator research findings
- Generic issue 87 : flexible wedge gate valve test program : phase II results and analysis
- Generic service water system risk-based inspection guide
- Geothermal R&D project report for period April 1, 1977 to September 30, 1977
- Geothermal direct applications hardware systems development and testing : 1979 summary report
- Geothermal reservoir assessment and confirmation program for direct heat application
- Geothermal resource exploration in Boise, Idaho
- ISLOCA research program : final report
- Implications for accident management of adding water to a degrading reactor core
- Insights for aging management of light water reactor components
- Instrumentation availability during severe accidents for a boiling water reactor with a Mark I containment
- Instrumentation availability for a pressurized water reactor with a large dry containment during severe accidents
- Integrated reliability and risk analysis system (IRRAS) version 2.0 user's guide
- Integrated reliability and risk analysis system (IRRAS) version 2.5
- Integrated reliability and risk analysis system (IRRAS), version 4.0
- Intentional depressurization accident management strategy for pressurized water reactors
- International code assessment and applications program : summary of code assessment studies concerning RELAP5/MOD2, RELAP5/MOD3, and TRAC-B
- Inventory and case studies of Louisiana, non-electric industrial applications of geopressured geothermal resources : final report
- Iodine-hydrogen peroxide as a disinfectant for fuel storage basin water
- LOFT experimental measurements uncertainty analyses
- Laboratory evaluation of Zeolite molecular sieve 3A for absorption of tritiated water vapor from HTGR fuel reprocessing off-gas
- Life assessment procedures for major LWR components
- Light water reactor lower head failure analysis
- Liquid-fluidized-bed heat exchanger design parameters
- Liquid-fluidized-bed heat exchanger flow distribution model
- Low-level radioactive waste disposal facility closure
- Lysimeter literature review
- Materials screening tests for the krypton 85 storage development program
- Metallographic and hardness examinations of TMI-2 lower pressure vessel head samples
- Methods evaluation and development for the monitoring of technetium-99 and selenium-79 in nuclear fuel reprocessing and waste solidificaton facility off-gas
- Methods evaluation for the continuous monitoring of carbon-14, krypton-85, and iodine-129 in nuclear fuel reprocessing and waste solidification facility off-gas
- Methods for review and evaluation of emergency procedure guidelines
- Microbial degradation of low-level radioactive waste
- Microbial-influenced cement degradation : literature review
- Models and Results Database (MAR-D), version 4.0 : reference manual
- Models for estimation of service life of concrete barriers in low-level radioactive waste disposal
- Motor-operated valve (MOV) actuator motor and gearbox testing
- Motor-operated valve research update
- Nuclear computerized library for assessing reactor reliability (NUCLARR)
- Nuclear computerized library for assessing reactor reliability (NUCLARR)
- Nuclear computerized library for assessing reactor reliability (NUCLARR)
- Nuclear computerized library for assessing reactor reliability (NUCLARR)
- Nuclear plant aging research on high pressure injection systems
- Off-gas cleanup system considerations for fluidized-bed radioactive waste calcination at the ICPP
- PBF severe fuel damage test 1-3 test results report
- Packaging supplier inspection guide
- Performance of intact and partially degraded concrete barriers in limiting fluid flow
- Performance of intact and partially degraded concrete barriers in limiting mass transport
- Pilot-plant development of a Rover waste calcination flowsheet
- Piping system response during high-level simulated seismic tests at the Heissdampfreaktor facility (SHAM test facility)
- Preliminary evaluation of snubber single failures
- Pressure-dependent fragilities for piping components : pilot study on Davis-Besse Nuclear Power Station
- Proceedings of the Second NRC/ASME Symposium on Pump and Valve Testing : held at Hyatt Regency Hotel, Washington, DC, July 21-23, 1992
- Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing : held at Hyatt Regency Hotel, Washington, DC, July 18-21, 1994
- Product removal and solids transport from fluidized-bed calciners /, by E. S. Grimmett, D. H. Munger ; prepared for the Department of Energy, Idaho Operations Office ..
- Quality assurance and verification of the MACCS code, version 1.5
- Quality assurance inspections for shipping and storage containers
- Quantifying reactor safety margins : application of code scaling, applicability, and uncertainty evaluation methodology to a large-break, loss-of-coolant accident
- Quantitative analysis of potential performance improvements for the dry PWR containment
- Quarterly progress report on welding technology development
- RELAP5 thermal-hydraulic analysis of the SNUPPS pressurized water reactor
- RELAP5 thermal-hydraulic analysis of the WNP1 pressurized water reactor
- RELAP5/MOD2 models and correlations
- RELAP5/MOD3 code manual
- RELAP5/MOD3 code manual
- Radiation degradation in EPICOR-II ion exchange resins / prepared by J.W. McConnell, Jr., D.A. Johnson, R.D. Sanders, Sr
- Radioactive Waste Management Complex : rocks, water, and waste management
- Radionuclide buildup in BWR reactor coolant recirculation piping
- Release of radionuclides and chelating agents from cement-solidified decontamination low-level radioactive waste collected from the Peach Bottom Atomic Power Station Unit 3
- Remote maintenance development
- Research and development plan for the slagging pyrolysis incinerator
- Residential space heating cost : geothermal vs conventional systems
- Residual life assessment of major light water reactor components : overview
- Review and development of common nomenclature for naming and labeling schemes for probabilistic risk assessment
- Review of current literature related to generic safety issue 15
- Review of the Brunswick Steam Electric Plant probabilisitic risk assessment
- Risk analysis of highly combustible gas storage, supply, and distribution systems in PWR plants
- Rover process verification studies : sintered metal filters blowback system
- Rover process verification studies : transport of dry solids
- Ruthenium behavior during calcination
- SAPHIRE technical reference manual : IRRAS/SARA version 4.0
- Screening methods for developing internal pressure capacities for components in systems interfacing with nuclear power plant reactor coolant systems
- Simplified containment event tree analysis for the Sequoyah ice condenser containment
- State and parameter estimation in a nuclear fuel pin using the extended Kalman filter
- Status report of physical and mechanical test data of alloy 718
- Steam generator tube failures
- Studies of human performance during operating events : 1990-1992
- Summary of 1991-1992 misadministration event investigations
- Summary of work completed under the environmental and dynamic equipment qualification research program (EDQP)
- Summary report for LOFT anticipated transient experiment series L6-8
- User's guide for simplified computer models for the estimation of long-term performance of cement-based materials
- Systems analysis programs for hands-on integrated reliability evaluations (SAPHIRE), version 5.0
- TMI-2 EPICOR-II resin/liner investigation : low-level waste data base development program for fiscal year 1989 : annual report
- TMI-2 nozzle examinations performed at the Idaho National Laboratory
- TMI-2 vessel investigation project integration report
- TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor
- TRAC-BF1/MOD1 : an advanced best-estimate computer program for BWR accident analysis
- TRAC-BF1/MOD1 models and correlations
- Technical evaluation of generic issue 113 : dynamic qualification and testing of large bore hydraulic snubbers
- Technical findings for proposed integrated resolution of generic issue 128, electric power reliability
- The effects of aging on compressive strength of low-level radioactive waste form samples
- The leachability of decontamination ion-exchange resins solidified in cement at operating nuclear power plants
- The potential application of microwave energy in solidifying high-level nuclear wastes
- The subsurface migration of radionuclides at the radioactive waste management complex, 1976-1977
- Thermal-hydraulic processes during reduced inventory operation with loss of residual heat removal
- Timing analysis of PWR fuel pin failures : draft report for comment
- Timing analysis of PWR fuel pin failures : final report
- Tooling for mechanized welding of large diameter pipe
- Uncertainty analysis of minimum vessel liquid inventory during a small-break LOCA in a B&W plant : an application of the CSAU methodology using the RELAP5/MOD3 computer code
- Uranium fission-rate monitors
- User's description of second-order error propagation (SOERP) computer code for statistically independent variables
- System analysis and risk assessment system (SARA) : version 4.0
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<div class="citation" vocab="http://schema.org/"><i class="fa fa-external-link-square fa-fw"></i> Data from <span resource="http://link.library.in.gov/resource/vw2ULIdqvuY/" typeof="Organization http://bibfra.me/vocab/lite/Organization"><span property="name http://bibfra.me/vocab/lite/label"><a href="http://link.library.in.gov/resource/vw2ULIdqvuY/">Idaho National Engineering Laboratory</a></span> - <span property="potentialAction" typeOf="OrganizeAction"><span property="agent" typeof="LibrarySystem http://library.link/vocab/LibrarySystem" resource="http://link.library.in.gov/"><span property="name http://bibfra.me/vocab/lite/label"><a property="url" href="http://link.library.in.gov/">Indiana State Library</a></span></span></span></span></div>
