Optical pyrometry measurement on oxidized zirconium alloy nuclear material cladding
Abstract
In order to improve the safety of nuclear power plant, loss-of-coolant accident experiments are
implemented in research reactor. In this framework, we develop an optical pyrometry device to measure
surface temperature (700-1200°C) of Zircaloy cladding without contact. The whole set-up of the
simplified device (under air, without radiation) and the measurement procedure including data treatment
based on bichromatic pyrometry are presented, as well as results for various temperature levels.
Temperature retrieval based on the hypothesis of emissivity ratio equal to a constant, is scanned over a
large wavelength range. A constant surface temperature is obtained on the spectral range of
measurement, confirming the relevancy of emissivity hypothesis. Differences between this non-contact
temperature measurement and a complementary thermocouple temperature measurement are also
discussed.
Origin : Files produced by the author(s)
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