Reflood experiments with a 4-rod bundle. Interim report. [PWR; BWR]
Experiments are reported on the reflooding of a four-rod bundle in a new radio-frequency heating facility. A range of flowrates and surface temperatures have been covered. The results show significant differences in the quenching rates of stainless-steel and zircaloy clad, and significant interaction between them in a mixed bundle. The results have been correlated utilizing conduction theory. Comments are made on the nature of the transient boiling curve.
- Research Organization:
- California Univ., Los Angeles (USA). Dept. of Chemical, Nuclear, and Thermal Engineering
- OSTI ID:
- 5460709
- Report Number(s):
- EPRI-NP-1277
- Country of Publication:
- United States
- Language:
- English
Similar Records
Quenching studies on a zircaloy rod bundle
Effects of high temperature and flow blockage on the reflood behavior of a 4-rod bundle. Final report. [PWR]
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210100 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALLOYS
BOILING
BWR TYPE REACTORS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
ENERGY TRANSFER
FILM BOILING
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
LOSS OF COOLANT
MECHANICS
MOCKUP
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
QUENCHING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STAINLESS STEELS
STEELS
STRUCTURAL MODELS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS