Civil Engineering Reference
In-Depth Information
Table 3.3
Design characteristics of the BWR power plants BWR-1,300 of Kraftwerk Union and
SWR-1,000 of AREVA [
15
,
16
]
BWR-1,300
(Kraftwerk Union)
SWR-1,000 (KERENA)
(AREVA)
Reactor power
Thermal
MW(th)
3,840
3,370
Electrical net
MW(e)
1,284
1,254
Plant efficiency (net)
%
35
37.2
Reactor core
Equivalent core diameter m
4.8
5.3
Active core height
m
3.74
3.0
Specific core power
kW(th)/l
56.8
51
Density
kW(th)/kg
U
28.2
24.7
Number of fuel elements
784
664
Total amount of fuel
(uranium mass)
kg U
136,000
136,300
Fuel element and control element
Fuel
UO
2
UO
2
U-235 fuel enrichment
average
w/%
4
5.4
Cladding material
Zircaloy
Zircaloy (Fe combined)
Cladding outer diameter mm
10.28
10.28
Cladding thickness
mm
0.62
0.62
Av. specific fuel rod
power
W/cm
129
116
Fuel assembly array
10
10 ATRIUM
12
12 ATRIUM
Control/absorber rod
type
Cruciform control element
inserted from the bottom
between a set of 4 fuel
assemblies
Cruciform control element
inserted from the bottom
between a set of 4 fuel
assemblies
Number of control
elements
193
157
Heat transfer system
Primary system
Total coolant flow rate
(core flow)
t/s
14.3
13.2
Coolant pressure
MPa
7.0
7.5
C
Feedwater temp.
216
220
C
Core coolant inlet temp.
278
278
C
Steam outlet temp.
286
289
Steam supply system
Steam generation
t/s
1.94
1.85
Steam pressure
MPa
7.0
7.3
Steam temperature
C
286
289
Fuel cycle
Average fuel burn up
MWd/ton
56,000
65,000
Refueling sequence
1/4 per 18 months
1/4 per 18 months
Average fissile fraction in spent fuel
- U-235
%
0.8
0.8
