Research Article
Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors
Table 2
Melting points for UO2 and ATF fuel materials.
| Fuel material | Melting point (°C) | Ref. |
| UO2 | 2847 | [24] | UN | 2680 | [25] | U3Si2 | 1665 | [24, 25] | U-8Mo | 1135 | [13] | SiC | 2457 | [10] |
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