Analysis of corrosion data for carbon steels in simulated salt repository brines and acid chloride solutions at high temperatures
Carbon steel is currently the leading candidate material for fabrication of a container for isolation of high level nuclear waste in a salt repository. Since brine entrapped in the bedded salt can migrate to the container by several transport processes, corrosion is an important consideration in the long-term performance of the waste package. A detailed literature search was performed to compile relevant corrosion data for carbon steels in anoxic acid chloride solutions, and simulated salt repository brines at temperatures between approx. 20 and 400/sup 0/C. The hydrolysis of Mg/sup 2 +/ ions in simulated repository brines containing high magnesium concentrations causes acidification at temperatures above 25/sup 0/C, which, in turn, influences the protective nature of the magnetite corrosion product layer on carbon steel. The corrosion data for the steels were analyzed, and an analytical model for general corrosion was developed to calculate the amount of penetration (i.e., wall thinning) as a function of time, temperature, and the pressure of corrosion product hydrogen than can build up during exposure in a closed system (e.g., a sealed capsule). Both the temperature and pressure dependence of the corrosion rate of steels in anoxic acid chloride solutions indicate that the rate-controlling partial reaction is the cathodic reduction of water to form hydrogen. Variations in the composition and microstructure of the steels or the concentration of the ionic species in the chloride solutions (provided that they do not change the pH significantly) do not appear to strongly influence the corrosion rate.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 7166407
- Report Number(s):
- CONF-880377-3; ON: DE88012030
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALLOYS
BRINES
CARBON STEELS
CHEMICAL REACTIONS
CHLORIDES
CHLORINE COMPOUNDS
CONTAINERS
CORROSION RESISTANCE
DECOMPOSITION
GEOLOGIC DEPOSITS
HALIDES
HALOGEN COMPOUNDS
HIGH-LEVEL RADIOACTIVE WASTES
HYDROLYSIS
IRON ALLOYS
IRON BASE ALLOYS
LYSIS
MANAGEMENT
MATERIALS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE STORAGE
RADIOACTIVE WASTES
SALT DEPOSITS
SOLVOLYSIS
STEELS
STORAGE
TEMPERATURE EFFECTS
WASTE MANAGEMENT
WASTE STORAGE
WASTES