EFFECT OF LITHIUM HYDROXIDE LEAKAGE ON THE HIGH-TEMPERATURE CORROSION OF ZIRCALOY-2
The corrosion and hydriding rates of Zircaloy-2 are greatly increased by high concentrations of LiOH in high temperature water. The possibility exists that this type of corrosion may be of concern in reactor systems employing Zircaloy pressure tubes and a coolant adjusted to pH 10 with LiOH. Concentrations of lithium hydroxide could occur at a steam water interface (e.g. a leak at a rolled or flanged joint between pressure tube and nozzle). Two experiments to simulate concentration of LiOH at a leaking mechanical joint have each resulted in corrosion approximately 100 times greater than the corrosion of Zircaloy-2 in pH 10 water at the same temperature (300 deg C) and for the same period of time. Polished cross sections of the highly corroded areas revealed only a small amount of hydriding (100 ppm). This was probably due to the small area of accelerated corrosion and the relatively large volume of sample. The corrosion product hydrogen absorbed could therefore be distributed in the bulk of the sample at levels of less than 100 ppm. (D.L.C.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-18-005743
- OSTI ID:
- 4154037
- Report Number(s):
- HW-78819
- Country of Publication:
- United States
- Language:
- English
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