Core flow distribution in a General Electric Boiling Water Reactor as measured in Quad Cities Unit 1
Technical Report
·
OSTI ID:7328953
Flow distribution at the inlet to the core of a General Electric boiling water reactor driven by jet pumps was studied experimentally at the Quad Cities 1 plant. Emphasis for this test was given to one-recirculation-pump operation with the equilizer valve closed. The flow test was conducted at atmospheric pressure and ambient temperature with all the fuel bundles in place and with the steam separator-dryer and vessel head off. Individual fuel bundle flow was measured with a specially fabricated flow measuring device at the exit of selected fuel bundles located symmetrically in the core. Results of the test indicated that flow through the various fuel bundles of the core during the one-pump operation mode does not vary more than +-1.9 percent from the average bundle flow rate at 95 percent confidence level, and this measured variation is randomly distributed over the core. Also, the two-pump data obtained from this test show essentially uniform flow distribution. This confirms the design assumption of uniform pressure distribution in the reactor lower plenum for both one- and two-pump operation. Since all jet-pump-driven boiling water reactors have similar hydraulic design bases with respect to the jet pump design and the lower plenum, this experimental program confirms that the pressure distribution for all of these BWRs is uniform.
- Research Organization:
- General Electric Co., San Jose, CA (USA). Atomic Power Equipment Dept.
- OSTI ID:
- 7328953
- Report Number(s):
- NEDO-10722A
- Country of Publication:
- United States
- Language:
- English
Similar Records
Core flow distribution in a modern boiling water reactor as measured in Monticello
BWR parallel flow recirculation system
Operational experience with zirconium-barrier fuel during cycle 8 of Quad Cities Unit 2
Technical Report
·
Fri Oct 01 00:00:00 EDT 1976
·
OSTI ID:7231360
BWR parallel flow recirculation system
Patent
·
Mon Jan 20 23:00:00 EST 1992
·
OSTI ID:5405251
Operational experience with zirconium-barrier fuel during cycle 8 of Quad Cities Unit 2
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6754867
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
COOLING SYSTEMS
DISTRIBUTION
ENRICHED URANIUM REACTORS
FLUID FLOW
POWER REACTORS
QUAD CITIES-1 REACTOR
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTORS
SPATIAL DISTRIBUTION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
COOLING SYSTEMS
DISTRIBUTION
ENRICHED URANIUM REACTORS
FLUID FLOW
POWER REACTORS
QUAD CITIES-1 REACTOR
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTORS
SPATIAL DISTRIBUTION
WATER COOLED REACTORS
WATER MODERATED REACTORS