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 materialMelting point (°C)Ref.

UO22847[24]
UN2680[25]
U3Si21665[24, 25]
U-8Mo1135[13]
SiC2457[10]