An Introduction to Probabilistic Fault Displacement Hazard Analysis in Site Evaluation for Existing Nuclear Installations
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Add to BasketTechnical Insights from Benchmarking Different Methods for Predicting Pipe Failure Rates in Water Cooled Reactors
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Reducing the Costs of Space Science Research Missions : Proceedings of a Workshop
Joint Committee on Technology for Space Science and Applications of th
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An Assessment of the National Institute of Standards and Technology Center for Neutron Research : Fiscal Year 2010
National Research Council
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Add to BasketDesign Safety Considerations for Water Cooled Small Modular Reactors Incorporating Lessons Learned from the Fukushima Daiichi Accident
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Add to BasketExperiences in Implementing Safety Improvements at Existing Nuclear Power Plants
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Add to BasketNuclear Power Reactors in the World, 2018 Edition
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Add to BasketRadiotracer Technologies for Wear, Erosion and Corrosion Measurement
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Add to BasketIntegrated Nuclear Infrastructure Review (INIR) : Ten Years of Lessons Learned
International Atomic Energy Agency
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Add to BasketAnalyses 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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Add to BasketEffective Management of Regulatory Experience for Safety
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Add to BasketCase 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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Add to BasketUnderstanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs) : Final Report of a Coordinated Research Project
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Add to BasketINPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Waste Management : INPRO Manual
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Add to BasketINPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Safety of Nuclear Reactors : INPRO Manual
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Add to BasketRegulatory Oversight of Human and Organizational Factors for Safety of Nuclear Installations
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Add to BasketProcessing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal : Results of a Coordinated Research Project
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Add to BasketPhenomenology, Simulation and Modelling of Accidents in Spent Fuel Pools : Proceedings of a Technical Meeting
International Atomic Energy Agency
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Add to BasketComputer Security Incident Response Planning at Nuclear Facilities
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