Mechanisms of LiOH degradation and H{sub 3}BO{sub 3} repair of ZrO{sub 2} films
- Univ. of Toronto, Ontario (Canada). Centre for Nuclear Engineering
During a program to elucidate the mechanisms by which LiOH accelerates the corrosion of zirconium alloys and boric acid inhibits this effect, specimens were exposed to 0.01, 0.1, and 1.0 M LiOH solutions at 300 C (573 K) or 360 C (673 K) with and without the addition of boric acid. Results showed that local dissolution of the ZrO{sub 2} films formed pores whose depth was a function of the LiOH concentration and probably also of the temperature, alloy composition, and structure. Below a critical LiOH concentration, only superficial porosity was developed in short experiments. Above this critical concentration porosity develops throughout the initially impervious oxide and no pretransition corrosion kinetics are observed. Below this critical concentration, no effect of LiOH is observed on the pretransition oxidation kinetics until pores and cracks start to develop in the oxide prior to the oxidation rate transition. At this point LiOH can concentrate in the freshly developed pores by chemical extraction of water from the solution in the pores to form new ZrO{sub 2}. Once the critical LiOH concentration is reached in the pores, enlargement or extension of the pores can occur by dissolution. This process should occur beneath the relatively untouched pretransition oxide when the bulk solution is not concentrated enough to attack the oxide surface. Hydrothermal redeposition of much of the dissolved ZrO{sub 2} occurs on specimen surfaces or within the porous oxide. Boric acid has no effect on ZrO{sub 2} dissolution by LiOH. It is considered that in concentrated solutions the solubility product of some complex lithium zirconate borate can be exceeded and this can plug the pores. In dilute solutions, therefore, boric acid can only operate inside the porous oxide film, where the chemical concentration mechanism should be equally effective for both LiOH and H{sub 3}BO{sub 3}.
- Sponsoring Organization:
- Organization of CANDU Industries, Toronto, ON (Canada); Natural Sciences and Engineering Research Council of Canada, Ottawa, ON (Canada)
- OSTI ID:
- 479433
- Report Number(s):
- CONF-950926-; TRN: 97:010502
- Resource Relation:
- Conference: 11. international symposium on zirconium in the nuclear industry, Garmisch-Partenkirchen (Germany), 11-14 Sep 1995; Other Information: PBD: 1996; Related Information: Is Part Of Zirconium in the nuclear industry: Eleventh international symposium; Bradley, E.R. [ed.] [Sandvik Special Metals Corp., Kennewick, WA (United States)]; Sabol, G.P. [ed.] [Westinghouse Electric Corp., Pittsburgh, PA (United States)]; PB: 911 p.; American Society for Testing and Materials STP 1295
- Country of Publication:
- United States
- Language:
- English
Similar Records
CHEMICAL PROCESSING TECHNOLOGY QUARTERLY PROGRESS REPORT, APRIL-JUNE 1962
Oxidation and salt corrosion of an Si{sub 2}N{sub 2}O-ZrO{sub 2} composite material