Security During the Lifetime of a Nuclear Facility (French Edition)
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Review of Fuel Failures in Water Cooled Reactors 2006–2015 (Chinese Edition)
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Site Evaluation for Nuclear Installations : Safety Requirements
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An Introduction to Probabilistic Fault Displacement Hazard Analysis in Site Evaluation for Existing Nuclear Installations
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Technical Insights from Benchmarking Different Methods for Predicting Pipe Failure Rates in Water Cooled Reactors
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Milestones in the Development of a National Infrastructure for Nuclear Power (Spanish Edition)
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Impacts of Radionuclide Releases Into the Marine Environment
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Supporting Sampling and Sample Preparation Tools for Isotope and Nuclear Analysis
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Human Resource Management for New Nuclear Power Programmes
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Design and Construction of Nuclear Power Plants to Facilitate Decommissioning
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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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International Safeguards in the Design of Facilities for Long Term Spent Fuel Management
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Safety Aspects of Nuclear Power Plants in Human Induced External Events: Assessment of Structures : Review of Recent Accomplishments, Challenges and Technologies
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Dependability Assessment of Software for Safety Instrumentation and Control Systems at Nuclear Power Plants
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Strategic Planning for Research Reactors
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Benchmarks of Fuel Burnup and Material Activation Computational Tools Against Experimental Data for Research Reactors
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Nuclear Power Reactors in the World, 2018 Edition
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Industrial Safety Guidelines for Nuclear Facilities
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The Radiological Accident in Chilca
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Analyses Supporting Conversion of Research Reactors from High Enriched Uranium Fuel to Low Enriched Uranium Fuel : The Case of the Miniature Neutron Source Reactors
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Effective Management of Regulatory Experience for Safety
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Buried and Underground Piping and Tank Ageing Management for Nuclear Power Plants
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Radiation Safety of X Ray Generators and Other Radiation Sources Used for Inspection Purposes and for Non-Medical Human Imaging
IAEA
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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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