Effect of self-ion bombardment damage on high temperature oxidation behavior of Zircaloy-4
- 1. Tsinghua Univ., Beijing, BJ (China). Dept. of Materials Science and Engineering
Description
In order to simulate the oxidation behavior of Zircaloy-4 in pressurized water reactors, it was bombarded with 190 keV Zr+ ions at liquid nitrogen temperature up to a dose of 8 x 1016 ions/cm2 and was then oxidized in pure oxygen at 923 K and 133.3 Pa. Auger electron spectroscopy (AES) and X-ray photoelectronic spectroscopy (XPS) were employed to investigate the distribution and the valence of oxygen and zirconium ions inside the oxide films before and after bombardment. It was found that: (1) the Zr+ ion bombardment enhanced the oxidation of Zircaloy-4 and resulted in the oxidation weight gain at a dose of 8 x 1016 ions/cm2 which was four times greater than that of the unbombarded sample; (2) the valence of zirconium ions in the oxide films was classified as Zr0, Zr1+, Zr2+, Zr3+ and Zr4+ and the higher valence of zirconium ions increased after the bombardment; (3) the irradiation oxidation damage function was established and (4) a regression formula describing the relation between the oxidation weight gain and dpa (displacement per atom) was obtained. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 254
- Journal Issue
- 2-3
- Journal Page Range
- p. 266-270
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 29052094
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AUGER ELECTRON SPECTROSCOPY; KEV RANGE 100-1000; OXIDATION; PHOTOELECTRON SPECTROSCOPY; PWR TYPE REACTORS; RADIATION EFFECTS; TEMPERATURE RANGE 0065-0273 K; TIME DEPENDENCE; WEIGHT; ZIRCALOY 4; ZIRCONIUM IONS
- Descriptors DEC
- ALLOY-ZR98SN-4; ALLOYS; CHARGED PARTICLES; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; ELECTRON SPECTROSCOPY; ENERGY RANGE; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IONS; IRON ADDITIONS; KEV RANGE; MATERIALS; POWER REACTORS; REACTORS; SPECTROSCOPY; TEMPERATURE RANGE; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 21 refs.