The structural layer enclosing nuclear fuel, retaining fuel and fission products while transferring heat to a coolant. Its pressure loading, chemical compatibility and irradiation response must remain consistent with its required geometry and integrity.
Alloys based on zirconium, widely used for water-reactor nuclear fuel cladding because of their useful combination of low neutron absorption and material properties. Corrosion, hydrogen uptake, creep and irradiation-induced dimensional changes limit performance.
Mechanical contact and load transfer between expanding or cracking fuel pellets and their enclosing nuclear fuel cladding. Local stress depends on clearance, fuel deformation and the cladding's evolving material properties.
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