Radiogenic Lead with Dominant Content of ²⁰⁸Pb: New Coolant and Neutron Moderator for Innovative Nuclear Facilities

Table 7

Thermal-hydraulic parameters of models with axial blanket.

Parameter	Thickness of axial blanket (cm)
	0	10	20	40	60
Coolant velocity (relative units)	1	1.02	1.05	1.08	1.10
The number of fuel rods (relative units)	1	1.10	1.15	1.16	1.17
Pressure drop required for coolant flow through fuel assembly (relative units)	1	1.11	1.28	1.61	1.78