Module 06
Module 06
Boiling
Boiling Water
Water Reactors
Reactors
(BWR)
(BWR)
Prof.Dr
Prof.Dr.
. H.
H. B
Bö
öck
ck
Vienna University of Technology / Austria
Vienna University of Technology / Austria
Atominstitute
Atominstitute
Stadionallee
Stadionallee 2,
2,
1020 Vienna, Austria
1020 Vienna, Austria
boeck@ati.ac.at
boeck@ati.ac.at
BWR Basics
BWR Basics
Technical Data
Technical Data
Safety Features
Safety Features
Reactivity Control
Reactivity Control
Fuel Assemblies
Fuel Assemblies
Reactor Pressure Vessel
Reactor Pressure Vessel
Development of
Development of BWR
BWR
s
s
SWR
SWR-
-1000
1000
ABWR
ABWR
Contents
Contents
H
H2
2O as coolant
O as coolant and
and moderator
moderator
Pressure in water/ steam cycle: 70 bar (7
Pressure in water/ steam cycle: 70 bar (7 MPa
MPa)
)
Boiling of water in the core
Boiling of water in the core
Temperature about 300
Temperature about 300 º
ºC
C
Steam transferred directly from core to turbine
Steam transferred directly from core to turbine
generator after passing steam/ water separator
generator after passing steam/ water separator
Average
Average power
power density
density in
in core
core: 50
: 50 kW/ litre
kW/ litre
Burn
Burn-
-up
up: ca. 55.000
: ca. 55.000 MWd/ t
MWd/ t U
U
Thermal
Thermal net
net efficiency
efficiency: 34.1%
: 34.1%
BWR Basics
BWR Basics
BWR
BWR Generations
Generations
Example
Example:
: The
The BWR
BWR Kr
Krü
ümmel
mmel
Built
Built
1984
1984
by
by KWU
KWU
1260
1260 MW
MWe
enet
net
3690
3690 MW
MWth
th