Safety Culture Practices for the Regulatory Body
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Design Safety Considerations for Water Cooled Small Modular Reactors Incorporating Lessons Learned from the Fukushima Daiichi Accident
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Experiences in Implementing Safety Improvements at Existing Nuclear Power Plants
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Nuclear Forensics: Beyond the Science : Summary of a Technical Meeting
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Radiotracer Technologies for Wear, Erosion and Corrosion Measurement
IAEA
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Effective Management of Regulatory Experience for Safety
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Understanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs) : Final Report of a Coordinated Research Project
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INPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Waste Management : INPRO Manual
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INPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Safety of Nuclear Reactors : INPRO Manual
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INPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Safety of Nuclear Fuel Cycle Facilities : INPRO Manual
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Regulatory Oversight of Human and Organizational Factors for Safety of Nuclear Installations
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Criteria for Radionuclide Activity Concentrations for Food and Drinking Water
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Development of a Common Framework for Addressing Climate and Environmental Change in Post-closure Radiological Assessment of Solid Radioactive Waste Disposal : Report of Working Group 6 Common Framewo
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Accident Tolerant Fuel Concepts for Light Water Reactors : Proceedings of a Technical Meeting Held at Oak Ridge National Laboratories, United States of America, 13-16 October 2014
IAEA
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Integrated Approach to Safety Classification of Mechanical Components for Fusion Applications
IAEA
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Dissimilar Metal Weld Inspection, Monitoring and Repair Approaches
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Deployment Indicators for Small Modular Reactors : Methodology, Analysis of Key Factors and Case Studies
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In-vessel Melt Retention and Ex-vessel Corium Cooling : Summary of a Technical Meeting
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Seismic Isolation Systems for Nuclear Installations
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Improvement of Effectiveness of In-Service Inspection in Nuclear Power Plants
IAEA
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Benchmarking of Computational Fluid Dynamics Codes for Fuel Assembly Design : Results of a Coordinated Research Project
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Quality Assurance and Quality Control in Nuclear Facilities and Activities : Good Practices and Lessons Learned
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Considerations on Performing Integrated Risk Informed Decision Making
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Benchmarking of Computational Fluid Dynamics Codes for Reactor Vessel Design : Results of a Coordinated Research Project
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