The objective of this project was tQ provide an assessment of several methods by which the temperature of a commercial nuclear power plant reactor pressure vessel could be measured during an annealing process. This project was a coordinated effort between DOE's Office of Nuclear Energy, Science and Technology; DOE's Light Water Reactor Technology Center at Sandia National Laboratories; and the Electric Power Research Institute's NonDestructive Evaluation Center.Ball-thermocouple probes similar to those described in NUREG/CR-5760, spring-loaded, metalsheathed thermocouple probes, and air-suspended thermocouples were investigated in experiments that heated a section of an RPV wall to simulate a thermal annealing treatment. A parametric study of ball material, emissivity, thermal conductivity, and thermocouple function locations was conducted. Also investigated was a sheathed thermocouple failure mode known as "shunting'' (electrical breakdown of insulation separating the thermocouple wires).Large errors were found between the temperature as measured by the probes and the true RPV wall temperature during heat-up and cool-down. At the annealing soak temperature, in this case 454°C [850"F], all sensors measured the same temperature within about k5% (23.6"C [42.5"F]).Because of these errors, actual RPV wall heating and cooling rates differed from those prescribed (by up to 29%). Shunting does not appear to be a problem under these conditions. The large temperature measurement errors led to the development of a thermal model that predicts the RPV wall temperature from the temperature of a ball-probe. Comparisons between the model and the experimental data for ball-probes indicate that the model could be a useful tool in predicting the actual RPV temperature based on the indicated ball-probe temperature. The model does not predict the temperatures as well for the spring-loaded and air-suspended probes.' Retired. MASTER Investigation of RPV Temperature Measurement Methods AcknowledgmentsThis work was performed at Sandia National Laboratories, Albuquerque, New Mexico, by personnel from the Department of Energy's Light Water Reactor Technology Center, Advanced Nuclear Power Technology Department (6471) ' . . Investigation of RPV Temperature Measurement Methods Figures Executive SummaryNeutron exposure in the beltline region of a reactor pressure vessel (RPV) causes the steel to become less ductile, lowering its resistance to fiacture and making the RPV more susceptible to pressurized thermal shock (PTS). PTS occurs when an RPV is depressurized, then repressurized at a lower temperature. Annealing is the only known embrittlement management technique that restores material properties to the RPV steel. Thermal annealing returns the embrittled portions of the RPV (e.g., beltline welds] to a more ductile state and may be used to extend the service life of the plant. This investigation was undertaken to determine how accurately various methods measure the true temperature of an RPV wall during a thermal annea...
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