Cassava Production Guidelines for Food Security and Adaptation to Climate Change in Asia and Africa
IAEA
Paperback
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Integrated Approach to Safety Classification of Mechanical Components for Fusion Applications
Unconformity-Related Uranium Deposits
Thorium Resources as Co- and By-products of Rare Earth Deposits
Heavy Water Reactor Moderator Effectiveness as a Backup Heat Sink During Accidents
Fuel Modelling in Accident Conditions (FUMAC)
A Methodology to Evaluate the Effectiveness of Training in Nuclear Facilities
Hybrid Simulation to Assess Performance of Seismic Isolation in Nuclear Power Plants
Classification, Selection and Use of Nuclear Power Plant Simulators for Education and Training
Regulatory Control of the Safety of Ion Radiotherapy Facilities
Developments in the Analysis and Management of Combustible Gases in Severe Accidents in Water Cooled Reactors following the Fukushima Daiichi Accident
International Atomic Energy Agency
Environmental Impact Assessment of the Drawdown of the Chernobyl NPP Cooling Pond as a Basis for Its Decommissioning and Remediation
Experiences in Implementing Safety Improvements at Existing Nuclear Power Plants
Radiotracer Technologies for Wear, Erosion and Corrosion Measurement
INPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Waste Management
Understanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs)
INPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Safety of Nuclear Reactors
Effective Management of Regulatory Experience for Safety
Safety Culture Practices for the Regulatory Body
Nuclear Forensics: Beyond the Science
Application of the Graded Approach to Post-closure Safety Assessment for the Disposal of Disused Sealed Radioactive Sources in Boreholes
Landscape Salinity and Water Management for Improving Agricultural Productivity
Condition Monitoring and Incipient Failure Detection of Rotating Equipment in Research Reactors
Reliability Data for Research Reactor Probabilistic Safety Assessment
Implementation and Effectiveness of Actions Taken at Nuclear Power Plants following the Fukushima Daiichi Accident
INPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Safety of Nuclear Fuel Cycle Facilities
Quality Assurance and Quality Control in Nuclear Facilities and Activities
Challenges for Coolants in Fast Neutron Spectrum Systems
Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions
Benchmarking of Computational Fluid Dynamics Codes for Reactor Vessel Design
Development of a Common Framework for Addressing Climate and Environmental Change in Post-Closure Radiological Assessment of Solid Radioactive Waste Disposal
Considerations on Performing Integrated Risk Informed Decision Making
Seismic Isolation Systems for Nuclear Installations
Assessing Behavioural Competencies of Employees in Nuclear Facilities
Benchmarking of Computational Fluid Dynamics Codes for Fuel Assembly Design
In-Vessel Melt Retention and Ex-Vessel Corium Cooling
Case Study on Assessment of Radiological Environmental Impact from Potential Exposure
Pathways to Energy from Inertial Fusion
Geochemical and Mineralogical Characterization of Uranium and Thorium Deposits
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Industrial Applications of Sealed Radioactive Sources
Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors
Analysis of Options and Experimental Examination of Fuels for Water Cooled Reactors with Increased Accident Tolerance (ACTOF)
Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit
Optimizing Soil, Water and Nutrient Use Efficiency in Integrated Cropping-Livestock Production Systems
Environmental Transfer of Radionuclides in Japan Following the Accident at the Fukushima Daiichi Nuclear Power Plant
Methodology for a Safety Case of a Dual Purpose Cask for Storage and Transport of Spent Fuel
Approaches to Management of Requirement Specifications for Nuclear Facilities throughout Their Life Cycle
Underground Disposal Concepts for Small Inventories of Intermediate and High Level Radioactive Waste
An Introduction to Practical Industrial Tomography Techniques for Non-destructive Testing (NDT)
Modern Neutron Detection
Operating Experience from Events Reported to the IAEA/NEA Fuel Incident Notification and Analysis System (FINAS)
Assuring the Competence of Nuclear Power Plant Contractor Personnel
Considerations for Environmental Impact Assessment for Small Modular Reactors
Applicability of Design Safety Requirements to Small Modular Reactor Technologies Intended for Near Term Deployment
Ageing Management of Nuclear Power Plants during Delayed Construction Periods, Extended Shutdown and Permanent Shutdown Prior to Decommissioning
Production of Emerging Radionuclides towards Theranostic Applications: Copper-61, Scandium-43 and -44, and Yttrium-86
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 Data
A Preliminary Inventory and Assessment of Uranium Resources in Mine Wastes
Protection against Exposure Due to Radon Indoors and Gamma Radiation from Construction Materials
Occupational Radiation Protection during the Decommissioning of Nuclear Installations
Neutron Scattering with Low and Medium Flux Neutron Sources
Progress on Pellet–Cladding Interaction and Stress Corrosion Cracking Experimentation, Modelling and Methodologies Applied to Support the Flexible Operation of Nuclear Power Plants: Report of a Techni
Seismic Instrumentation System and Its Use in Post-Earthquake Decision Making at Nuclear Power Plants
Integrated Nuclear Infrastructure Review (INIR)
Experiences of Member States in Building a Regulatory Framework for the Oversight of New Nuclear Power Plants
Development of Tolerant Crop Cultivars for Abiotic Stresses to Increase Food Security
Status and Trends in Pyroprocessing of Spent Nuclear Fuels
Application of a Graded Approach in Regulating the Safety of Radiation Sources
Level 1 Probabilistic Safety Assessment Practices for Nuclear Power Plants with CANDU-Type Reactors
Spent Fuel Performance Assessment and Research
Structural Materials for Heavy Liquid Metal Cooled Fast Reactors
Considerations of Safety and Utilization of Subcritical Assemblies
Soil–Plant Transfer of Radionuclides in Non-Temperate Environments
Technical Review of Acceptance Criteria for Pressurized Heavy Water Reactor Fuel
Assessment of Vulnerabilities of Operating Nuclear Power Plants to Extreme External Events
