Corrosion experience in nuclear waste processing at Battelle Northwest. [In-Can Melter vitrification; interim canister storage in water]

Conference · Mon Nov 01 00:00:00 EST 1976

OSTI ID:7325008

Slate, S C; Maness, R F

Emphasis is on corrosion as related to waste storage canister. Most work has been done in support of the In-Can Melter (ICM) vitrification system. It is assumed that the canister goes through the ICM process and is then stored in a water basin. The most severe corrosion effect seen is oxidation of stainless steel (SS) surfaces in contact with gases containing oxygen during processing. The processing temperature is near 1100/sup 0/C and furnace atmosphere, used until now, has been air with unrestricted flow to the furnace. The oxidation rate at 1100/sup 0/C is 15.8 g/cm/sup 2/ for 304L SS. Techniques for eliminating this corrosion currently being investigated include the use of different materials, such as Inconel 601, and the use of an inert cover gas. Corrosion due to the waste melt is not as rapid as the air oxidation. This effect has been studied extensively in connection with the development of a metallic crucible melter at Battelle. Data are available on the corrosion rates of several waste compositions in contact with various materials. Long-term compatibility tests between the melt and the metal have been run; it was found the corrosion rates due to the melt or its vapor do not pose a serious problem to the waste canister. However, these rates are high enough to preclude the practical use of a metallic melter. Interim water storage of the canister may be a problem if proper corrective measurements are not taken.The canister may be susceptible to stress corrosion cracking (SCC) because it will be sensitized to some extent and it will be nearly stressed to yield. The most favorable solution to SCC involves minimizing canister sensitization and stress plus providing good water quality control. It has been recommended to keep the chlorine ion concentration below 1 ppM and the pH above 10. At these conditions no failures of 304L are predicted due to SCC. It is concluded that corrosion of a canister used during the In-Can Melter process and interim storage can be controlled. (DLC)

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (USA)
• Sponsoring Organization: USDOE
• DOE Contract Number: E(45-1)-1830
• OSTI ID: 7325008
• Report Number(s): BNWL-SA-6002; CONF-770303-4; TRN: 77-009022
• Resource Relation: Conference: Corrosion/77 NACE meeting, San Francisco, CA, USA, 14 Mar 1977
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
RADIOACTIVE WASTE PROCESSING
SOLIDIFICATION
RADIOACTIVE WASTE STORAGE
CORROSION
AIR
CONTAINERS
HAPO
MELTING
OXIDATION
STAINLESS STEEL-304L
STRESS CORROSION
WATER
ALLOYS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
FLUIDS
GASES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HYDROGEN COMPOUNDS
IRON ALLOYS
IRON BASE ALLOYS
MANAGEMENT
MATERIALS
NATIONAL ORGANIZATIONS
NICKEL ALLOYS
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PROCESSING
STAINLESS STEELS
STEELS
STORAGE
US AEC
US ERDA
US ORGANIZATIONS
WASTE MANAGEMENT
WASTE PROCESSING
WASTE STORAGE
052001* - Nuclear Fuels- Waste Processing