Hot-wall corrosion testing of simulated high level nuclear waste

Technical Report · Sun Jan 01 04:00:00 EST 1995

DOI:https://doi.org/10.2172/10110494· OSTI ID:10110494

Chandler, G T; Zapp, P E; Mickalonis, J I

Three materials of construction for steam tubes used in the evaporation of high level radioactive waste were tested under heat flux conditions, referred to as hot-wall tests. The materials were type 304L stainless steel alloy C276, and alloy G3. Non-radioactive acidic and alkaline salt solutions containing halides and mercury simulated different high level waste solutions stored or processed at the United States Department of Energy`s Savannah River Site. Alloy C276 was also tested for corrosion susceptibility under steady-state conditions. The nickel-based alloys C276 and G3 exhibited excellent corrosion resistance under the conditions studied. Alloy C276 was not susceptible to localized corrosion and had a corrosion rate of 0.01 mpy (0.25 {mu}m/y) when exposed to acidic waste sludge and precipitate slurry at a hot-wall temperature of 150{degrees}C. Type 304L was susceptible to localized corrosion under the same conditions. Alloy G3 had a corrosion rate of 0.1 mpy (2.5 {mu}m/y) when exposed to caustic high level waste evaporator solution at a hot-wall temperature of 220{degrees}C compared to 1.1 mpy (28.0 {mu}/y) for type 304L. Under extreme caustic conditions (45 weight percent sodium hydroxide) G3 had a corrosion rate of 0.1 mpy (2.5 {mu}m/y) at a hot-wall temperature of 180{degrees}C while type 304L had a high corrosion rate of 69.4 mpy (1.8 mm/y).

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 10110494
• Report Number(s): WSRC-MS--94-0367; CONF-950304--9; ON: DE95005007
• Country of Publication: United States
• Language: English

Related Subjects

052001
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CORROSION RESISTANCE
EVAPORATION
EXPERIMENTAL DATA
HALIDES
HEAT FLUX
HIGH-LEVEL RADIOACTIVE WASTES
MERCURY
NICKEL BASE ALLOYS
RADIOACTIVE WASTE MANAGEMENT
REMEDIAL ACTION
SAVANNAH RIVER PLANT
SODIUM HYDROXIDES
STAINLESS STEEL-304L
STEAM LINES
VITRIFICATION
WASTE PROCESSING