IAEA · 2.605 obras en el catálogoObras — página 37NNeutron Generators for Analytical PurposesNeutron Generators for Analytical PurposesCComparison of Heavy Water Reactor Thermalhydraulic Code PredComparison of Heavy Water Reactor Thermalhydraulic Code Predictions with Small Break LOCA Experimental DataQQuality Assurance Programme for Computed TomographyQuality Assurance Programme for Computed TomographyMMonitoring for Compliance with Remediation Criteria for SiteMonitoring for Compliance with Remediation Criteria for SitesSSafety Culture in Pre-Operational Phases of Nuclear Power PlSafety Culture in Pre-Operational Phases of Nuclear Power Plant ProjectsSSafety Case and Safety Assessment for the Disposal of RadioaSafety Case and Safety Assessment for the Disposal of Radioactive WasteSSources and Measurements of Radon and Radon Progeny Applied Sources and Measurements of Radon and Radon Progeny Applied to Climate and Air Quality StudiesEEnvironmental Modelling for Radiation SafetyEnvironmental Modelling for Radiation SafetyIImproved and Harmonized Quality Control for Expanded Tsetse Improved and Harmonized Quality Control for Expanded Tsetse Production, Sterilization and Field ApplicationFFuel Modelling at Extended BurnupFuel Modelling at Extended BurnupLLiquid Metal Coolants for Fast Reactors Cooled by Sodium, LeLiquid Metal Coolants for Fast Reactors Cooled by Sodium, Lead and Lead-Bismuth EutecticAApplication of Radiotracer Techniques for Interwell StudiesApplication of Radiotracer Techniques for Interwell StudiesMManagement System Standards : Comparison Between IAEA GS-R-3Management System Standards : Comparison Between IAEA GS-R-3 and ASME NQA-1-2008 and NQA-1a-2009 AddendaMManagement System Standards : Comparison Between IAEA GS-R-3Management System Standards : Comparison Between IAEA GS-R-3 and ISO 9001 : 2008 : Comparison Between IAEA GS-R-3 and ISO 9001VVolcanic Hazards in Site Evaluation for Nuclear InstallationVolcanic Hazards in Site Evaluation for Nuclear InstallationsUUse of a Graded Approach in the Application of the Safety ReUse of a Graded Approach in the Application of the Safety Requirements for Research ReactorsDDevelopment of Novel Adsorbents and Membranes by Radiation IDevelopment of Novel Adsorbents and Membranes by Radiation Induced Grafting for Selective Separation in Environmental and Industrial ApplicationsIIdentification of Vital Areas at Nuclear FacilitiesIdentification of Vital Areas at Nuclear FacilitiesEEfficient Water Management in Water Cooled ReactorsEfficient Water Management in Water Cooled ReactorsLLicensing the First Nuclear Power PlantLicensing the First Nuclear Power PlantRResearch Reactors : Safe Management and Effective UtilizatioResearch Reactors : Safe Management and Effective UtilizationHHuman Resource Development for Introducing and Expanding NucHuman Resource Development for Introducing and Expanding Nuclear Power ProgrammesAAssessment of Nuclear Energy Systems Based on a Closed NucleAssessment of Nuclear Energy Systems Based on a Closed Nuclear Fuel Cycle with Fast ReactorsSStructural Materials for Liquid Metal Cooled Fast Reactor FuStructural Materials for Liquid Metal Cooled Fast Reactor Fuel Assemblies AnteriorPágina 37 de 109Siguiente
CComparison of Heavy Water Reactor Thermalhydraulic Code PredComparison of Heavy Water Reactor Thermalhydraulic Code Predictions with Small Break LOCA Experimental Data
QQuality Assurance Programme for Computed TomographyQuality Assurance Programme for Computed Tomography
MMonitoring for Compliance with Remediation Criteria for SiteMonitoring for Compliance with Remediation Criteria for Sites
SSafety Culture in Pre-Operational Phases of Nuclear Power PlSafety Culture in Pre-Operational Phases of Nuclear Power Plant Projects
SSafety Case and Safety Assessment for the Disposal of RadioaSafety Case and Safety Assessment for the Disposal of Radioactive Waste
SSources and Measurements of Radon and Radon Progeny Applied Sources and Measurements of Radon and Radon Progeny Applied to Climate and Air Quality Studies
IImproved and Harmonized Quality Control for Expanded Tsetse Improved and Harmonized Quality Control for Expanded Tsetse Production, Sterilization and Field Application
LLiquid Metal Coolants for Fast Reactors Cooled by Sodium, LeLiquid Metal Coolants for Fast Reactors Cooled by Sodium, Lead and Lead-Bismuth Eutectic
AApplication of Radiotracer Techniques for Interwell StudiesApplication of Radiotracer Techniques for Interwell Studies
MManagement System Standards : Comparison Between IAEA GS-R-3Management System Standards : Comparison Between IAEA GS-R-3 and ASME NQA-1-2008 and NQA-1a-2009 Addenda
MManagement System Standards : Comparison Between IAEA GS-R-3Management System Standards : Comparison Between IAEA GS-R-3 and ISO 9001 : 2008 : Comparison Between IAEA GS-R-3 and ISO 9001
VVolcanic Hazards in Site Evaluation for Nuclear InstallationVolcanic Hazards in Site Evaluation for Nuclear Installations
UUse of a Graded Approach in the Application of the Safety ReUse of a Graded Approach in the Application of the Safety Requirements for Research Reactors
DDevelopment of Novel Adsorbents and Membranes by Radiation IDevelopment of Novel Adsorbents and Membranes by Radiation Induced Grafting for Selective Separation in Environmental and Industrial Applications
IIdentification of Vital Areas at Nuclear FacilitiesIdentification of Vital Areas at Nuclear Facilities
EEfficient Water Management in Water Cooled ReactorsEfficient Water Management in Water Cooled Reactors
RResearch Reactors : Safe Management and Effective UtilizatioResearch Reactors : Safe Management and Effective Utilization
HHuman Resource Development for Introducing and Expanding NucHuman Resource Development for Introducing and Expanding Nuclear Power Programmes
AAssessment of Nuclear Energy Systems Based on a Closed NucleAssessment of Nuclear Energy Systems Based on a Closed Nuclear Fuel Cycle with Fast Reactors
SStructural Materials for Liquid Metal Cooled Fast Reactor FuStructural Materials for Liquid Metal Cooled Fast Reactor Fuel Assemblies