Need and procedure for calibration of fuel rod simulators. [PWR]
Conference
·
OSTI ID:6918277
An experimental thermocouple calibration procedure and four-part calibration program, ORTCAL (ORNL Thermocouple Calibration), have been developed to supply FRS performance information to the inverse heat conduction model and program ORINC. Case studies have shown that failure to fully classify FRSs with regard to component physical properties, gaps, etc., can result in severe errors during inverse calculations of the driving potential at the surface of the FRS (..delta..T), the spatial and temporal history of the heat flow within the FRS, and the surface heat flux.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6918277
- Report Number(s):
- CONF-801091-7
- Country of Publication:
- United States
- Language:
- English
Similar Records
ORTCAL: a code for THTF heater rod thermocouple calibration. [PWR]
Progress report on return to nucleate boiling in electrically heated rod bundles under simulated PWR blowdown conditions
INCAP: a finite element program for one-dimensional nonlinear inverse heat conduction analysis. [PWR LOCA conditions]
Technical Report
·
Wed Jan 31 23:00:00 EST 1979
·
OSTI ID:6414431
Progress report on return to nucleate boiling in electrically heated rod bundles under simulated PWR blowdown conditions
Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6517674
INCAP: a finite element program for one-dimensional nonlinear inverse heat conduction analysis. [PWR LOCA conditions]
Technical Report
·
Sun Jul 01 00:00:00 EDT 1979
·
OSTI ID:6004544
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
CALIBRATION
FUEL ELEMENTS
FUEL RODS
LOSS OF COOLANT
MEASURING INSTRUMENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
TEST FACILITIES
THERMOCOUPLES
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
CALIBRATION
FUEL ELEMENTS
FUEL RODS
LOSS OF COOLANT
MEASURING INSTRUMENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
TEST FACILITIES
THERMOCOUPLES
WATER COOLED REACTORS
WATER MODERATED REACTORS