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Analysis of Options and Experimental Examination of Fuels for Water Cooled Reactors with Increased Accident Tolerance (ACTOF)

Final Report of a Coordinated Research Project

English IAEA-TECDOC-1921 978-92-0-114120-0
178 179 18.00 2020

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There is high interest in new fuel types with increased accident tolerance. These range from using an oxidation resistant coating on zirconium based cladding to alternate fuel and cladding materials. These new fuels/claddings under development must be licensed before being deployed industrially and therefore research is being undertaken to assess their behaviour in various conditions. This publication arises from an IAEA coordinated research project (CRP) dealing with the acquisition of data through experiments on new fuel types and cladding materials and the development of modelling capacity to predict the behaviour of the components and the integral performance of accident tolerant fuel designs under normal and transient conditions. Demonstrations of improvements under severe accident conditions were documented. Several coated cladding materials were produced, tested, characterized and analysed in round robin tests carried out within the CRP. For improvement and validation of fuel performance codes, several benchmarks were organized to compare and analyse predictions of the extended codes. The findings and conclusions of the CRP are summarized in this publication.

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ACTOF, Analysis, Options, Examination, Fuel, WCR, Water Cooled Reactor, Accident, Tolerance, Oxidation Resistant Coating, Zirconium, Zirconium Based Cladding, Alternate Fuel, Cladding, CRP, Coordinated Research Project, Reliability, Operational Reliability, Safety, NPP, Nuclear Power Plant, Accident Mitigation, ATF, Accident Tolerant Fuel, Materials, Properties, Materials Properties, Thermophysical, Mechanical, Thermal and Irradiation Creep, Swelling, Oxidation, Burst Failure Criterion, Specific Heat, Thermal Conductivity, Thermal Expansion, Young's Modulus, Poisson's Ratio, Emissivity, Volumetric Thermal Expansion, Elastic Constant, Creep, Yield Strength, Irradiation Swelling, Irradiation, Alloy 348, Round Robin Test, Sample Production, Long Term Corrosion, Facility, Conditions, Experimental, Methods, High Temperature Oxidation, Modelling, Modelling Benchmark, Fuel Performance, Results, Benchmark Results, ATR, Advanced Test Reactor, BWR, Boiling Water Reactor, LWR, Light Water Reactor, PHWR, Pressurized Heavy Water Reactor, PWR, Pressurized Water Reactor, WWER, Water Cooled Water Moderated Power Reactor

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