The e-learning module “General fuel overview, design, fuel fabrication, surveillance, and qualification process” is part of the Nuclear Fuel Engineering, Fabrication and Operation Behaviour course and consist of the 6 lectures.Content: This module comes in six lectures and provides the basic knowledge on nuclear fuel (design and fuel fabrication processes), thermal-mechanical and irradiation behaviour of fuel rods, fuel surveillance (fuel reliability and leaker monitoring) and fuel qualification aspects.Learning objectivesThe objective of these e-learning module is to provide a high-level guidance in taking a systematic approach to nuclear fuel design, fabrication, and nuclear fuel behaviour during irradiation.Duration: 45 min per each lecture (around 270 min for module) Language availability: EnglishTarget Audience for the e-Learnings: students, young professional, regulators, operators, high level government officials
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Module 1: General fuel overview, design, fuel fabrication, surveillance, and qualification process
Self-directed
Certificate available
Related courses
Related publications
• IAEA PRIS database • Advanced fuel technology and performance, IAEA-TECDOC 352, 1985 • Fuel Performance and Fission Product Behavior in Gas-Cooled Reactors, IAEA-TECDOC-978, 1997 • Poolside inspection, repair, and reconstitution of LWR fuel elements, IAEA-TECDOC-1050, 1998 • Technical and economic limits to fuel burnup extension, IAEA TECDOC-1299, 2002 • Status and Advances in MOX Fuel Technology, IAEA Technical report series n°415, 2003 • Fuel Failure in Water Reactors: Causes and Mitigation, IAEA-TECDOC-1345, 2003 • Development of protocols for corrosion and deposits evaluation in pipes by radiography, IAEA-TECDOC-1445, 2005 • Post-irradiation examination and in-pile measurement techniques for water reactor fuels, IAEA-TECDOC-1535, 2009 • Status of Minor Actinide Fuel Development, NES No. NF-T-4.6, 2009 • Review of Fuel Failures in Water Cooled Reactors, IAEA NES No. NF-T-2.1, 2010 • High Temperature Gas Cooled Reactor Fuels and Materials, IAEA-TECDOC-1645, 2010 • Hot Cell Post-Irradiation Examination and Poolside Inspection of Nuclear Fuel, IAEA TECDOC-1693, 2013 • Design, manufacturing and irradiation behavior of fast reactor fuel, TECDOC-1689 (iaea.org), 2013 • Review of Fuel Failures in Water Cooled Reactors (2006–2015), IAEA NES No. NF-T-2.5, 2019 • Design of the reactor core for nuclear power plants. IAEA SAFETY STANDARDS SERIES No. SSG-52 Technical Review of Acceptance Criteria for Pressurized Heavy Water Reactor Fuel, IAEA-TECDOC-1926, 2020 • Progress on Pellet–Cladding Interaction and Stress Corrosion Cracking, IAEA-TECDOC-1960, 2021 Fuel Behavior under Transient and LOCA Conditions, IAEA TECDOC-1320, 2022
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