PWR FLECHT SEASET 161-rod bundle flow blockage task, task plan report
This report presents a descriptive plan of tests for the 161-Rod Bundle Flow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Separate Effects and Systems Effects Test Program (FLECHT SEASET). This task will consist of forced and gravity reflooding tests utilizing electrical heater rods to simulate PWR nuclear core fuel rod arrays. All tests will be performed with a cosine axial power profile. These tests will be used to determine effects of flow blockage configurations on reflooding behavior and to aid in assessment/development of computational models in predicting reflooding behavior of flow blockage configurations.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Energy Systems Div.
- OSTI ID:
- 6596341
- Report Number(s):
- EPRI-NP-1458
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ENERGY TRANSFER
FLOW BLOCKAGE
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
LIQUID FLOW
MECHANICS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
SAFETY
SPECIFICATIONS
TEMPERATURE DISTRIBUTION
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ENERGY TRANSFER
FLOW BLOCKAGE
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
LIQUID FLOW
MECHANICS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
SAFETY
SPECIFICATIONS
TEMPERATURE DISTRIBUTION
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS