CORROSION OF REACTOR STRUCTURAL MATERIALSnIN HIGH-TEMEERATURE WATER II. STATIC CORROSION BEHAVIOR AT 600 TO 680℉

摘要

Possible structural materials for use in the primary coolant system and for fuel element fabrication in a voter-cooled and -moderated reactor were extensively corrosion-tested in static water end various aqueous media at 600 and 680ºF. Both AISI Type 304 and AISI Type 347 stainless steels were found to react with water at these temperatures at a rate of 3 to 5 mg of metal/dm2/500 hr. Carbon steel (ASTM A201) corroded at a rate approximately 10 times greater (40 mg/dm2/mo). Steels containing 2 1/4 and 5% chromium corroded at about 80 mg/dm2/mo.