Optical pyrometry measurement on oxidized zirconium alloy nuclear material cladding - CEA - Commissariat à l’énergie atomique et aux énergies alternatives Access content directly
Conference Papers Year : 2016

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.
Fichier principal
Vignette du fichier
201600000430.pdf (898.87 Ko) Télécharger le fichier
Origin : Files produced by the author(s)
Loading...

Dates and versions

cea-02442351 , version 1 (16-01-2020)

Identifiers

  • HAL Id : cea-02442351 , version 1

Cite

B. Bouvry, L. Ramiandrisoa, C. Cheymol, C. Gallou, H. Maskrot, et al.. Optical pyrometry measurement on oxidized zirconium alloy nuclear material cladding. 7th European Thermal-Sciences Conference, Jun 2016, Cracovie, Poland. ⟨cea-02442351⟩
21 View
40 Download

Share

Gmail Facebook X LinkedIn More