Peace and Security in Northeast Asia : Nuclear Issue and the Korean Peninsula
Peter Hayes
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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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Nuclear Power Reactors in the World, 2018 Edition
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Effective Management of Regulatory Experience for Safety
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Case Studies on the Development of a Comprehensive Report to Support the Decision Making Process for a Nuclear Power Programme
International Atomic Energy Agency
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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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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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Approaches for Modelling of Radioecological Data to Identify Key Radionuclides and Associated Parameter Values for Human and Wildlife Exposure Assessments : Report of Working Group 4: Modelling and Da
International Atomic Energy Agency
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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
IAEA
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Quality Assurance and Quality Control in Nuclear Facilities and Activities : Good Practices and Lessons Learned
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Occupational Radiation Protection during the Decommissioning of Nuclear Installations : Main Aspects of Management, Planning and Conduct
International Atomic Energy Agency
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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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