Research Article
Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core
| Position | Material | Density (kg·m−3) | Heat conduction coefficient (W·m−1 K−1) | Specific heat capacity (J·g−1 K−1) |
| Fuel | U3Si2-Al | 6030 | 50.7 | 0.892 + 0.00046T − 0.71 × (0.749 + 0.00038 T) | Cladding | 6061-O aluminum alloy | 2700 | 131.25 + 8.33 × 10−2 T | 0.897 |
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