Nuclear power plants -- Risk assessment
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The concept Nuclear power plants -- Risk assessment represents the subject, aboutness, idea or notion of resources found in Indiana State Library.
The Resource
Nuclear power plants -- Risk assessment
Resource Information
The concept Nuclear power plants -- Risk assessment represents the subject, aboutness, idea or notion of resources found in Indiana State Library.
- Label
- Nuclear power plants -- Risk assessment
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- (EG-IN)693015
65 Items that share the Concept Nuclear power plants -- Risk assessment
Context
Context of Nuclear power plants -- Risk assessmentSubject of
- A cause-defense approach to the understanding and analysis of common cause failures
- A probabilistic evaluation of the safety of Babcock & Wilcox nuclear reactor power plants with emphasis on historically observed operational events
- A technique for human error analysis (ATHEANA) : technical basis and methodology description
- Accident management information needs
- Aging assessment of surge protective devices in nuclear power plants
- Aging data analysis and risk assessment : development and demonstration study
- An approach for estimating the frequencies of various containment failure modes and bypass events : draft report for comment
- An approach for estimating the frequencies of various containment failure modes and bypass events : final report
- An assessment of steam-explosion-induced containment failure
- 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
- Assessment of ice-condenser containment performance issues
- BWR and PWR off-normal event descriptions
- Common-cause failure event insights
- Comparison and application of quantitative human reliability anlaysis methods for the risk methods integration and evaluation program (RMIEP) : final report
- Development and use of risk-based inspection guides
- Draft regulatory guide DG-1139 : risk-informed, performance-based fire protection for existing light-water nuclear power plants
- 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
- Elements of an approach to performance-based regulatory oversight
- Feasibility of developing risk-based rankings of pressure boundary systems for inservice inspection
- Generic risk insights for Westinghouse and Combustion Engineering pressurized water reactors
- Incorporating aging effects into probabilistic risk assessment : a feasibility study utilizing reliability physics models
- Industry based performance indicators for nuclear power plants
- Integrated systems analysis of the PIUS reactor
- Managing aging in nuclear power plants : insights from NRC maintenance team inspection reports
- Methods for dependency estimation and system unavailability evaluation based on failure data statistics
- Methods for the elicitation and use of expert opinion in risk assessment : phase I, a critical evaluation and directions for future research
- Nuclear plant aging research on high pressure injection systems
- Nuclear plant service water system aging degradation assessment
- PRA applications program for inspection at Calvert Cliffs Unit 1 nuclear power plant
- PRA applications program for inspection at Oconee Unit 3
- Pressurized melt ejection into water pools
- Prioritization of TIRGALEX, recommended components for further aging research
- Probabilistic accident consequence uncertainty analysis : early health effects uncertainty assessment
- Probabilistic accident consequence uncertainty analysis : late health effects uncertainty assessment
- Probabilistic accident consequence uncertainty analysis : uncertainty assessment for deposited material and external doses
- Probabilistic accident consequence uncertainty analysis : uncertainty assessment for internal dosimetry
- Probability and consequences of rapid boron dilution in a PWR : a scoping study
- Probability of failure in BWR reactor coolant piping
- Procedures for the external event core damage frequency analyses for NUREG-1150
- Quantitative analysis of potential performance improvements for the dry PWR containment
- Quantitative evaluation of surveillance test intervals including test-caused risks
- Regulatory Guide 1.200 : an approach for determining the technical adequacy of probabilistic risk assessment results for risk-informed activities
- Regulatory Guide 1.203 : transient and accident analysis methods
- Regulatory Guide 1.205 : risk-informed, performance-based fire protection for existing light-water nuclear power plants
- 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 1.204 : guidelines for lightning protection of nuclear power plants
- Risk analysis of highly combustible gas storage, supply, and distribution systems in PWR plants
- Risk assessment for the intentional depressurization strategy in PWRs
- Risk assessment of severe accident-induced steam generator tube rupture
- Risk comparison of scheduling prevention maintenance during shutdown vs. during power operation for PWRs
- Risk comparisons of scheduling preventive maintenance for boiling water reactors during shutdown and power operations
- Risk impact of BWR technical specifications requirements during shutdown
- Risk importance of containment and related ESF system performance requirements
- Risk methods insights gained from fire incidents
- Risk-based maintenance modeling : prioritization of maintenance importances and quantification of maintenance effectiveness
- Shippingport station aging evaluation
- Software safety hazard analysis
- Some observations on risk-informing appendices A and B to 10 CFR part 50 : prepared for the Advisory Committee on Reactor Safeguards
- Specific topics in severe accident management
- Technical specification action statements requiring shutdown : a risk perspective with application to the RHR/SSW systems of a BWR
- Technical study of spent fuel pool accident risk at decommissioning nuclear power plants
- The technical basis for the NRC's guidelines for external risk communication
- The technical basis for the NRC's guidelines for external risk communication
- Value-impact assessment for a candidate operating procedure upgrade program
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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/Pa-pBjjbhys/" typeof="CategoryCode http://bibfra.me/vocab/lite/Concept"><span property="name http://bibfra.me/vocab/lite/label"><a href="http://link.library.in.gov/resource/Pa-pBjjbhys/">Nuclear power plants -- Risk assessment</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>
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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/Pa-pBjjbhys/" typeof="CategoryCode http://bibfra.me/vocab/lite/Concept"><span property="name http://bibfra.me/vocab/lite/label"><a href="http://link.library.in.gov/resource/Pa-pBjjbhys/">Nuclear power plants -- Risk assessment</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>
