IAEA TECDOC – serie

INPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Waste Management

INPRO Manual

INPRO Methodology for Sustainability Assessment of Nuclear Energy Systems: Safety of Nuclear Fuel Cycle Facilities

INPRO Manual

Experiences of Member States in Building a Regulatory Framework for the Oversight of New Nuclear Power Plants

Country Case Studies

Model Regulations for the Use of Radiation Sources and for the Management of the Associated Radioactive Waste

Improving the Understanding of Irradiation Creep Behaviour in Nuclear Graphite Models and Mechanisms

Improving the Understanding of Nitrate Sources in Freshwater Systems Through Linking Isotopes and Contaminants of Emerging Concern

Final Report of a Coordinated Research Project

Life Cycle Asset Management of Uranium Mining and Processing Facilities

Quality Assurance and Quality Control in Nuclear Facilities and Activities

Good Practices and Lessons Learned

Waste Minimization During the Life Cycle of Nuclear Power Plants

Material Properties of Unirradiated Uranium–Molybdenum (U–Mo) Fuel for Research Reactors

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 Technical Meeting

Environmental Transfer of Radionuclides in Japan Following the Accident at the Fukushima Daiichi Nuclear Power Plant

Report of Working Group 4 Transfer Processes and Data for Radiological Impact Assessment Subgroup 2 on Fukushima Data: IAEA Programme on Modelling and Data for Radiological Impact Assessments (MODARIA II)

Implementation and Effectiveness of Actions Taken at Nuclear Power Plants Following the Fukushima Daiichi Accident

Operating Experience from Events Reported to the IAEA/NEA Fuel Incident Notification and Analysis System (FINAS)

Studies of Temporal Trends of Pollution in Selected Coastal Areas by the Application of Isotopic and Nuclear Techniques

Current Approaches to the Analysis of Design Extension Conditions with Core Melting for New Nuclear Power Plants