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

Table 6

Serpent burnup calculation steps.

Step	Burnup (MWd/kg(U))
	0
	0.03
	0.06
⋯	⋯
	0.21
	0.25
	0.30
	0.45
	0.60
⋯	⋯
	1.20
	1.50
	1.80
	2.10
	2.50
	3.00
	3.50
⋯	⋯
	6.00
	7.00
	8.00
	9.00
	10.00
⋯	⋯
	30.00