Behavior of a nine-rod PWR bundle under power-cooling-mismatch conditions
Conference
·
OSTI ID:5908848
An experiment to characterize the behavior of a nine-rod pressurized water reactor (PWR) fuel bundle operating during power-cooling-mismatch (PCM) conditions has been conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL). The experiment, designated Test PCM-5, is part of a series of PCM experiments designed to evaluate light water reactor (LWR) fuel rod response under postulated accident conditions. Test PCM-5 was the first nine-rod bundle experiment in the PCM test series. The primary objectives and the results of the experiment are described.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5908848
- Report Number(s):
- CONF-791103-19
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fuel rod behavior in a nine-rod bundle tested in film boiling. [PWR]
In-pile post-DNB behavior of a nine-rod PWR-type fuel bundle
Response of unirradiated and irradiated PWR fuel rods tested under power-cooling-mismatch conditions
Conference
·
Thu Jan 25 23:00:00 EST 1979
·
OSTI ID:6321640
In-pile post-DNB behavior of a nine-rod PWR-type fuel bundle
Conference
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:5595584
Response of unirradiated and irradiated PWR fuel rods tested under power-cooling-mismatch conditions
Journal Article
·
Sat Dec 31 23:00:00 EST 1977
· Nucl. Saf.; (United States)
·
OSTI ID:6741176
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
FILM BOILING
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENT FAILURE
PHASE TRANSFORMATIONS
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
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
FILM BOILING
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENT FAILURE
PHASE TRANSFORMATIONS
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS