NE 502 Project
Fall 2015
Determine the maximum thermal power a PWR with the following system characteristics can operate under natural
circulation if the coolant exit temperature in the hot channel is to remain subcooled at a system pressure of 2250
psia. The reactor coolant system consist of the reactor vessel, 4 hot legs, 4 steam generators and four cold legs. The
vessel, hot leg and cold legs can be considered commercial steel. The fuel rods and steam generator tubes can be
considered smooth drawn tubing. The secondary side steam pressure can be assumed to be 1000 psia. You may
assume a reactor heat flux profile of the form
  (z  ) 

q( z )  q0 sin 
 He 
Problem Data
Reactor Vessel and Core
Rod Pitch
Rod Diameter
Number of Fuel Assemblies
Rod Array
Number of Spacer Grids
Grid Loss Coefficient
Core Height
Core Inlet Loss Coefficient
Core Outlet Loss Coefficient
Power Peaking Factor
Axial Peaking Factor
Fraction of Energy Deposity in Fuel
Vessel ID
Core Barrel OD
Downcomer Length
Downcomer Loss Coefficient
0.496 inches
0.374 inches
193
17 x 17
8
.5
150 inches
0.5
0.5
2.4
1.5
0.97
173 inches
157.6 inches
21 ft
4.5
Hot Leg (each Hot Leg)
Length
Diameter
Hot Leg Equivalent L/D
Hot Leg Inlet Loss Coefficient
20 ft
2.42 ft
20
1.5
Steam Generator (each steam generator)
Bundle Inlet Loss Coefficient (referenced to tube velocity)
0.5
Bend Equivalent L/D
55
Average tube length
66.8 ft
Tube Inner Diameter
0. 6075 inches
Number of tubes
6633
Cold Leg (each cold leg)
Length
Diameter
Cold Leg Inlet Loss Coefficient
Cold Leg Equivalent L/D
40 ft
2.29 ft
0.5
18