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

Table 3

ATF case table analyzed.

Case	Fuel	Cladding	Target BU
			(MWh/kgU)
	Uranium dioxide	Zircaloy-4	200 (NU)
	Uranium dioxide	Zircaloy-4	600
	UO2 + 3% SiC by volume	Zircaloy-4	NU, 200, 600
	UO2 + 3% SiC by volume	SiC	200
	UO2 + 3% SiC by volume	Zr/FeCrAl	200
	UO2 + 6% SiC by volume	Zircaloy-4	200
	UO2 + 10% SiC by volume	Zircaloy-4	200
	Uranium nitride	Zircaloy-4	NU, 600
	UN + 3% U3Si2 by volume	Zircaloy-4	NU
	UN + 6% U3Si2 by volume	Zircaloy-4	NU
	UN + 10% U3Si2 by volume	Zircaloy-4	NU
	UN + 10% ZrN by volume	Zircaloy-4	NU
	U-9Mo	Zircaloy-4	200
	FCM, UO2 kernels in SiC, 40% packing, 700 μm diameter	Zircaloy-4	NU, 200, 600,
	FCM, UO2 kernels in SiC, 45% packing, 700 μm diameter	Zircaloy-4	200,
	FCM, UO2 kernels in SiC, 35% packing, 700 μm diameter	Zircaloy-4	200,
	FCM, UO2 kernels in SiC, 40% packing, 650 μm diameter	Zircaloy-4	200,
	FCM, UO2 kernels in SiC, 40% packing, 750 μm diameter	Zircaloy-4	200,
	FCM, UO2 kernels in SiC, 50% packing, 700 μm diameter	Zircaloy-4	200,
	FCM, UO2 kernels in SiC, 55% packing, 700 μm diameter	Zircaloy-4	200,
	FCM, UN kernels in SiC, 40% packing, 700 μm diameter	Zircaloy-4	200,
	FCM, UN kernels in SiC, 45% packing, 700 μm diameter	Zircaloy-4	200,
	FCM, UN kernels in SiC, 35% packing, 700 μm diameter	Zircaloy-4	200,
	FCM, UN kernels in SiC, 50% packing, 700 μm diameter	Zircaloy-4	200,
	FCM, UN kernels in SiC, 55% packing, 700 μm diameter	Zircaloy-4	200,
	FCM, UN TRISO in SiC, 55% packing, 700 μm diam. kernels	Zircaloy-4

indicates exit burnup of 4044 MWh/bundle.