Multidimensional effects in the thermal response of fuel rod simulators. [PWR]
One of the primary objectives of the Oak Ridge National Laboratory Pressurized-Water Reactor Blowdown Heat Transfer Separate-Effects Program is the determination of the transient surface temperature and surface heat flux of fuel pin simulators (FPSs) from internal thermocouple signals obtained during a loss-of-coolant experiment (LOCE) in the Thermal-Hydraulics Test Facility. This analysis requires the solution of the classical inverse heat conduction problem. The assumptions that allow the governing differential equation to be reduced to one dimension can introduce significant errors in the computed surface heat flux and surface temperature. The degree to which these computed variables are perturbed is addressed and quantified.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6764007
- Report Number(s):
- CONF-801091-5; TRN: 81-000144
- Resource Relation:
- Conference: International symposium on fuel rod simulators-development and application, Gatlinburg, TN, USA, 22 Oct 1980
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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HEATERS
TEMPERATURE GRADIENTS
PERFORMANCE
LOSS OF COOLANT
TEST FACILITIES
PWR TYPE REACTORS
HEAT TRANSFER
REACTOR SAFETY
SIMULATION
THERMOCOUPLES
ACCIDENTS
ENERGY TRANSFER
FUEL ELEMENTS
MEASURING INSTRUMENTS
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220900* - Nuclear Reactor Technology- Reactor Safety
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