PWR FLECHT SEASET 163-Rod Bundle Flow Blockage Task data report. NRC/EPRI/Westinghouse report No. 13, August-October 1982
This report presents data from the 163-Rod Bundle Blow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Systems Effects and Separate Effects Test Program (FLECHT SEASET). The task consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. These tests were designed to determine effects of flow blockage and flow bypass on reflooding behavior and to aid in the assessment of computational models in predicting the reflooding behavior of flow blockage in rod bundle arrays.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Energy Systems Div.
- OSTI ID:
- 5371354
- Report Number(s):
- NUREG/CR-3314; EPRI-NP-3268; WCAP-10307; ON: DE84900702
- Country of Publication:
- United States
- Language:
- English
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CORE FLOODING SYSTEMS
ECCS
ELECTRIC HEATING
ENGINEERED SAFETY SYSTEMS
FLOW BLOCKAGE
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
HEATING
PERFORMANCE
PWR TYPE REACTORS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTORS
SIMULATION
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS