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HIGH TEMPERATURE OXIDATION OF NB-CONTAINING ZR ALLOY CLADDING IN LOCA CONDITIONS

  • Chuto, Toshinori (Fuel Safety Research Group, Nuclear Safety Research Center) ;
  • Nagase, Fumihisa (Fuel Safety Research Group, Nuclear Safety Research Center) ;
  • Fuketa, Toyoshi (Fuel Safety Research Group, Nuclear Safety Research Center)
  • Published : 2009.03.30

Abstract

In order to evaluate high-temperature oxidation behavior of the advanced alloy cladding under LOCA conditions, isothermal oxidation tests in steam were performed with cladding specimens prepared from high burnup PWR fuel rods that were irradiated up to 79 MWd/kg. Cladding materials were $M5^{(R)}$ and $ZIRLO^{TM}$, which are Nb-containing alloys. Ring-shaped specimens were isothermally oxidized in flowing steam at temperatures from 1173 to 1473 K for the duration between 120 and 4000s. Oxidation rates were evaluated from measured oxide layer thickness and weight gain. A protective effect of the preformed corrosion layer is seen for the shorter time range at the lower temperatures. The influence of pre-hydriding is not significant for the examined range. Alloy composition change generally has small influence on oxidation in the examined temperature range, though $M5^{(R)}$ shows an obviously smaller oxidation constant at 1273 K. Consequently, the oxidation rates of the high burnup $M5^{(R)}$ and $ZIRLO^{TM}$ cladding are comparable or lower than that of unirradiated Zircaloy-4 cladding.

References

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Cited by

  1. Treatment of the Equations of Metal Oxidation Rates at Nuclear Power Plants and Thermal Power Plants in Terms of Thermodynamics vol.65, pp.9, 2018, https://doi.org/10.1134/S0040601518090069