Abstract
Results of immersion tests of UNS N06625 (alloy 625), UNS S31609 (alloy 316 L), Ni-20Cr alloy and Nb coupons exposed to oxygenated ammoniacal sulphate solution at supercritical water oxidation (SCWO) conditions are presented. The corrosion behavior of the alloy 316 L (UNS S31603) SCWO reactor tubing is also presented under the same conditions. Immersion coupons corroded at a rate not exceeding 40 mm yr-1 while the reactor tube itself corroded at a rate of between 160-1500 mm yr-1, depending on which length of the reactor is considered to have corroded. Morphological and chemical analysis of the oxides present on the coupon samples suggest that iron oxides, which had initially precipitated on the corroding alloy 316 tube surface, were removed by heat flux-driven fluid mechanical action and transported through the reactor where they deposited on the coupons. Niobium was resistant to corrosion at the tested conditions.
Original language | British English |
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Pages (from-to) | 118-124 |
Number of pages | 7 |
Journal | Corrosion Science |
Volume | 52 |
Issue number | 1 |
DOIs | |
State | Published - Jan 2010 |
Keywords
- Corrosion
- High temperature
- Immersion testing
- Ni-Cr alloy
- Stainless steel
- Supercritical water