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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Sixty Years and Beyond - Contributing to Development : Proceedings of an International Conference Held in Vienna, 30 May-1 June 2017
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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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Advancing Implementation of Decommissioning and Environmental Remediation Programmes : CIDER Project: Baseline Report
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Nuclear Power Reactors in the World, 2018 Edition
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Radiotracer Technologies for Wear, Erosion and Corrosion Measurement
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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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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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Regulatory Oversight of Human and Organizational Factors for Safety of Nuclear Installations
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Quality Assurance for SPECT Systems
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Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal : Results of a Coordinated Research Project
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Computer Security Incident Response Planning at Nuclear Facilities
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Conducting Computer Security Assessments at Nuclear Facilities
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Use of the Benchmarking System for Operational Waste from WWER Reactors
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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
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Seismic Hazard Assessment in Site Evaluation for Nuclear Installations : Ground Motion Prediction Equations and Site Response
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Attributes of Full Scope Level 1 Probabilistic Safety Assessment (PSA) for Applications in Nuclear Power Plants
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Pathways to Energy from Inertial Fusion: Structural Materials for Inertial Fusion Facilities : Final Report of a Coordinated Research Project
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Challenges for Coolants in Fast Neutron Spectrum Systems
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