Assessment of the influence of surface thermocouples on the behavior of nuclear fuel rods during a large break LOCA
A second series of thermocouple effects tests (TC-3) is being conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL). These tests are designed to evaluate the influence of external surface thermocouples on the behavior of nuclear fuel rods during a large break loss-of-coolant accident (LOCA) experiment, which includes partial or total rod rewet during blowdown. Questions have been raised with regard to possible effects of surface thermocouples on the thermal behavior of in-pile and out-of-pile test rods. The TC-3 test series, currently being conducted at the PBF, is an extension of the TC-1 tests with four LOFT-type fuel rods contained in individual flow shrouds. The fuel rods are symmetrically positioned within a test train in the PBF in-pile tube in an environment similar to the LOFT test environment.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6575557
- Report Number(s):
- CONF-801053-11; TRN: 81-006665
- Resource Relation:
- Conference: 8. water reactor safety research information meeting, Gaithersburg, MD, USA, 27 Oct 1980
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL RODS
THERMOCOUPLES
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
ACCURACY
LOFT REACTOR
PBF REACTOR
REACTOR SAFETY
SIMULATION
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
MEASURING INSTRUMENTS
MECHANICS
PULSED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled