Civil Engineering Reference
In-Depth Information
UPPER TIE PLATE
LOCKING PIN
LOCKING DEVICE
FUEL ROD
DIMPLE CLIP
BAYONET
BOLT
10x10 FUEL
ROD ARRAY
WASHER
ULTRAFLOW
TM
SPACER
EGG-CRATE
SPACER WITH
SWIRL VANES
INNER STRIP
SPRING
COMPRESSION
SPRING
OUTER STRIP
SPRING
BAYONET PIN
PART-LENGTH
FUEL ROD
LOWER FUEL
ROD ADAPTER
CONNECTING BOLT
SPRING SLEEVE
WATER CHANNEL
LOWER TIE PLATE
Fig. 3.18
ATRIUM-10 boiling water reactor fuel element [
6
]
replaced by fresh fuel elements after 18 months. Fuel elements which have not
attained their maximum burnups at that time are reshuffled (moved to different
radial positions of the core).
The fuel rods contain gadolinium as a burnable neutron poison to compensate for
the burnup of fissile material and the build up of fission products during reactor
operation. The average power density in the core is 57 or 51 kW(th)/l and 28.2 or
24.7 kW(th)/kg uranium for the BWR-1,300 of Kraftwerk Union and SWR-1,000
(KERENA) of AREVA, respectively. The water inlet temperature in the lower part
of the core is 216
C or 220
C, the steam outlet temperature is 286
C or 289
C,
which corresponds to a saturation steam pressure of roughly 7.0 or 7.5 MPa
(Table
3.3
).
