CORROSION OF CARBON STEELS AND OTHER STEELS IN SIMULATED BOILING-WATER REACTOR ENVIRONMENT. PHASE II
ABS>Results are reported for the continuation of extensive corrosion testing of carbon steels and other steels exposed in a dynamic test loop simulating the various environments found in a nuclear boiling-water reactor system. Water and steam conditions were based on 10 to 20 ppm O and 1 to 2 ppm H in the 546 deg F saturated steam, a condition represent ative of the radiolytic water decomposition in boiling-water reactors. The pH of the high-purity water was about 7, and no chemical additives were used in the loop water. Tests were conducted to determine whether stress-corrosion cracking would occur; and the effect of simulated reactor startup and shutdown on corrosion, including pitting, rusting, and local attack. Results show that there was little, if any, difference in corrosion among the various steels tested containing up to 5% Cr. The corrosion rates of these steels averaged less than 10 mg/dm/ per month for 5289 hours of exposure. Stress-corrosion cracking was not detected in steels containing up to 5% Cr or in austenitic and ferritic stainless steels. Stress- corrosion cracking was detected in one specimen of hardened AISI Type 431 martensitic steel that was tested in steam-water environment. Pitting, rusting, and local attack of steels containing up to 5% Cr can occur in reactor-grade water during simulated reactor shutdowns when the water is at or near room temperature and has access to air. (auth)
- Research Organization:
- United States Steel Corp. Applied Research Lab., Monroeville, Penna.; General Electric Co. Vallecitos Atomic Lab., San Jose, Calif.
- NSA Number:
- NSA-16-015145
- OSTI ID:
- 4783558
- Report Number(s):
- NP-11552
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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