Corrosion of High-Level Waste Packaging Materials in Disposal Relevant Brines

Sensitivity Studies of Waste Package Performance in High-Level Waste Management

“…However, addition of nitrates (ratio of nitrate to chloride greater than 0.2) to the solutions suppressed crevice corrosion. German researchers conducted corrosion tests of Alloy C-4, a material less corrosion resistant than Alloy 22, in rock salt repository environments in a temperature range from 90°C to 200°C [5,9,10]. In NaCl rich brines, no localized corrosion was observed in this temperature range.…”

Understanding long-term corrosion of Alloy 22 container in the potential Yucca Mountain repository for high-level nuclear waste disposal

“…Fang and Staehle [20] noted that passive current density of Alloy 600 varied in about 3 orders-of-magnitude, depending on sulfur valence states in 10 À2 M solutions of sulfur oxyanion at pHs of 3.5 and 6, at 25°C (77°F) and 95°C (203°F), respectively. Smailos [51] showed that Hastelloy C4 (a family alloy of Alloy 22) showed pitting with 6 Â 10 À4 M Na 2 S at 150°C (302°F) in a NaCl-rich brine. However, the long-term corrosion test facility (LTCTF), for 5 years, in simulated Yucca Mountain environments did not show effects of sulfur influence, as this sulfur was not in detrimental ionic forms (e.g.…”