In-pile post-DNB behavior of a nine-rod PWR-type fuel bundle
Conference
·
OSTI ID:5595584
The results of an in-pile power-cooling-mismatch (PCM) test designed to investigate the behavior of a nine-rod, PWR-type fuel bundle under intermittent and sustained periods of high temperature film boiling operation are presented. Primary emphasis is placed on the DNB and post-DNB events including rod-to-rod interactions, return to nucleate boiling (RNB), and fuel rod failure. A comparison of the DNB behavior of the individual bundle rods with single-rod data obtained from previous PCM tests is also made.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5595584
- Report Number(s):
- CONF-800403-4
- Country of Publication:
- United States
- Language:
- English
Similar Records
Film boiling behavior of a pressurized water reactor type fuel bundle
Fuel rod behavior during test PCM-2. [PWR]
Behavior of a nine-rod PWR bundle under power-cooling-mismatch conditions
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Wed Dec 31 23:00:00 EST 1980
· Nucl. Technol.; (United States)
·
OSTI ID:5336723
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Technical Report
·
Sat Mar 31 23:00:00 EST 1979
·
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Behavior of a nine-rod PWR bundle under power-cooling-mismatch conditions
Conference
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:5908848
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
ACCIDENTS
BOILING
DEPARTURE NUCLEATE BOILING
ENERGY TRANSFER
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
MECHANICS
NUCLEATE BOILING
PHASE TRANSFORMATIONS
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
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
ACCIDENTS
BOILING
DEPARTURE NUCLEATE BOILING
ENERGY TRANSFER
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
MECHANICS
NUCLEATE BOILING
PHASE TRANSFORMATIONS
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS