Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors
Table 8
Required enrichment for ATF.
Fuel
Enrichment (wt% 235U) for target exit burnup
200 MWh/kgU
600 MWh/kgU
4044 MWh/bundle
UO2
0.711%
1.30%
0.711%
UO2 + 3% SiC (zirc4 clad)
0.72%
1.32%
0.72%
UO2 + 3% SiC (SiC clad)
0.711%
1.30%
0.72%
UO2 + 3% SiC (zirc4 + FeCrAl clad)
0.79%
1.42%
0.80%
UO2 + 6% SiC
0.72%
UO2 + 10% SiC
0.73%
1.34%
0.76%
UN
<0.711%; NU = 231.8 MWh/kgU
1.22%
UN + 3% U3Si2
<0.711%; NU = 231.2 MWh/kgU
UN + 6% U3Si2
<0.711%; NU = 230.6 MWh/kgU
UN + 10% U3Si2
<0.711%; NU = 229.7 MWh/kgU
UN + 10% ZrN
<0.711%; NU = 210.4 MWh/kgU
U-9Mo
0.93%
1.58%
0.87%
UO2 FCM 35% packing
1.07%
1.89%
UO2 FCM 40% packing
1.01%
1.80%
1.62%
UO2 FCM 45% packing
0.95%
1.43%
UO2 FCM 50% packing
0.91%
1.28%
UO2 FCM 55% packing
0.88%
1.60%
1.16%
UN FCM 35% packing
0.93%
1.28%
UN FCM 40% packing
0.89%
1.13%
UN FCM 45% packing
0.85%
1.02%
UN FCM 50% packing
0.82%
0.93%
UN FCM 55% packing
0.80%
0.87%
UN TRISO 55% packing
1.12%
2.25%
Cladding is zircaloy-4 unless otherwise indicated. Italicised values are for cases which were interpolated from supplemental data and not directly analyzed. Bolded values are values used for Figure 5. With bare kernel diameters of 650 µm, 700 µm, and 750 µm. Other cases were tested with only 700 µm kernels.
