This module consists of the 4 lectures and provides World overview, the description of main type of thermal reactors and its fuels (PWR, BWR, VVER, RBMK, AGR, Pressurized Heavy-Water Reactors); design parameters, specifications, fuel performance and fuel performance modelling for main type of LWRs; the main trends in LWRs fuels improvements.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 for main type of LWRs.Duration: around 45 min per each lecture (around 180 min for module) Language availability: EnglishTarget Audience for the e-Learnings: students, young professional, regulators, operators, high level government officials
Related publications
<p>• 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</p>
