Thermocouple signal sensitivity to the sheath thickness of thermal-hydraulic test facility indirectly heated electric fuel pin simulators
Analysis of data in large loss-of-coolant accident experimental facilities often requires extensive use of signals recorded from thermocouples embedded in indirectly heated electric fuel pin simulators (EFPS). These signals, converted to temperature, are used in the numerical determination of EFPS experimental conditions, inclusing transient surface temperature, transient surface heat flux, and transient internal radial temperature distribution. Important points that arise in uding the recorded thermocouple signals as a basis for subsequent analysis include (1) the effect of the distance that the thermocouple bead is located from the EFPS surface on the ability of the thermocouple to resolve rapidly changing boundary phenomena and (2) the extent that this depth influences the time response associated with the thermocouple. Several numerically solved EFPS transients (where boundary conditions were specified, and surface temperature, surface heat flux, and internal radial temperature histories were subsequently calculated) are presented in an effort to establish these two relationships and to form a foundation for recommending designs which will minimize the adverse effects of these relationships by specifying optimal thermocouple radial positions in future EFPSs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5392109
- Report Number(s):
- NUREG/CR-1347; ORNL/NUREG-62; ON: TI85015942
- Country of Publication:
- United States
- Language:
- English
Similar Records
TRANSIENT RESPONSE OF WATER TEMPERATURE THERMOCOUPLES
Multidimensional effects in the thermal response of fuel pin simulators. [PWR]
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL PINS
SIMULATORS
LOSS OF COOLANT
SIMULATION
PWR TYPE REACTORS
ELECTRIC HEATING
SENSITIVITY
THERMOCOUPLES
ACCIDENTS
ANALOG SYSTEMS
FUEL ELEMENTS
FUNCTIONAL MODELS
HEATING
MEASURING INSTRUMENTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled