Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors

Table 1

Uranium density comparison for UO₂ and ATF fuel.

Fuel material	Uranium density; (g/cm^3)	Ref.
UO2 (fully dense)	9.66	[11]
UO2 (5% porosity)	9.18
UN (fully dense)	13.55	[11]
U3Si2 (fully dense)	11.31	[11]
U-8Mo (fully dense)	16.1	[13]
FCM UO2/SiC (55% TRISO packing)	1.84	[10]
FCM UN/SiC (55% TRISO packing)	2.72	[10]