Page 201 - Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

172 Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

Fig. 4.7 NACIE facility.
Courtesy from ENEA.

Now, introducing the flow quality x and the slip ratio S, defined, respectively, as

1 α x ρ
_ m g w g l
x S ¼ α 1 x ρ
_ m g + _ m l w l g
the previous equation can be written as

ρ ρ
l g gH R
Δp DF ¼
1 x ρ g
1+ S
x ρ l
The total pressure drop along the flow path (Δp fric ) can be written as

1 X L X 2 2 H R 2
Δp fric ¼ f lo ρ l w 2 + Kρ w + Φ f lo ρ w
l
l
lo
2 i D e i j j D e,R