Results of the first nuclear blowdown test on single fuel rods (LOC-11 Series in PBF)
Conference
·
OSTI ID:6400249
This paper presents results of the first nuclear blowdown tests (LOC-11A, LOC-11B, LOC-11C) ever conducted. The Loss-of-Coolant Accident (LOCA) Test Series is being conducted in the Power Burst Facility (PBF) reactor at the Idaho National Engineering Laboratory, near Idaho Falls, Idaho, for the Nuclear Regulatory Commission. The objective of the LOC-11 tests was to obtain data on the behavior of pressurized and unpressurized rods when exposed to a blowdown similar to that expected in a pressurized water reactor (PWR) during a hypothesized double-ended cold-leg break. The data are being used for the development and verification of analytical models that are used to predict coolant and fuel rod pressure during a LOCA in a PWR.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6400249
- Report Number(s):
- CONF-781022-35
- Country of Publication:
- United States
- Language:
- English
Similar Records
Results of the first nuclear blowdown tests on single fuel rods (LOC-11 series in the PBF)
Heat transfer considerations for PBF first nuclear blowdown. [PWR]
Experiment data report for PBF-LOCA tests LOC-11B and 11C. [PWR]
Technical Report
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6702938
Heat transfer considerations for PBF first nuclear blowdown. [PWR]
Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6587917
Experiment data report for PBF-LOCA tests LOC-11B and 11C. [PWR]
Technical Report
·
Sun Oct 01 00:00:00 EDT 1978
·
OSTI ID:6541499
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
BLOWDOWN
FUEL ELEMENTS
LOSS OF COOLANT
PBF REACTOR
PULSED REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
TANK TYPE REACTORS
TEMPERATURE DISTRIBUTION
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
BLOWDOWN
FUEL ELEMENTS
LOSS OF COOLANT
PBF REACTOR
PULSED REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
TANK TYPE REACTORS
TEMPERATURE DISTRIBUTION
WATER COOLED REACTORS
WATER MODERATED REACTORS