Investigation of silver and iodine transport through silicon carbide layers prepared for nuclear fuel element cladding

Investigation of the Physical and Mechanical Properties of Silicon Carbide Prepared on an Industrial Scale

In this study, an industrial polycrystalline SiC tile was successfully sintered by pressureless sintering at 2150°C for 1 hour. The physical and mechanical properties of silicon carbide including density, hardness, bending strength, and fracture toughness were evaluated. The results indicated that the mentioned properties were 3.08 g.cm-3, 2503 HV0, 249.3 MPa, and 1.23 MPam0.5</...

Comparison of Silicon Carbide and Zircaloy4 Cladding during LBLOCA

The pressure and temperature histories on cladding inner and outer surfaces during of LBLOCA (Large Break Loss of Coolant Accident) are considered as boundary conditions for the structural analyses of three cladding materials. Since SiC (Silicon Carbide) has higher yield and ultimate strengths than Zry-4 (Zircaloy-4) under the same primary stresses, SiC has higher primary safety margin than Zry...

Behaviors of Nuclear Fuel Cladding During RIA

Comparison of Pellet-Cladding Mechanical Interaction for Zircaloy and Silicon Carbide Clad Fuel Rods in Pressurized Water Reactors

Contact between the outer surface of a fuel pellet and the inner surface of the fuel rod cladding can result in several kinds of undesirable behavior. As the pellet swells outward and the cladding creeps down, large stresses are generated in both the pellet and the cladding. This contact may exacerbate chemical degradation of the cladding and the stress may enable rapid propagation of cracks. B...

Perturbation Theory for Thin Cladding Layers on Silicon Photonic Systems