Simulation of the state of carbon steel n years after disposal with n years of corrosion product on its surface in a bentonite environment
- 1. Univ. of Tokyo (Japan)
- 2. Nakayama Steel Works, Ltd., Osaka (Japan)
Description
The use of bentonite as buffer and carbon steel as overpack material for the geological disposal of nuclear waste is under investigation. To better assess the long term integrity of the carbon steel overpack, a quantitative analysis of the corrosion behavior on the steel surface for time frames beyond that of feasible empirical determination is required. The state n years after disposal, consisting of Carbon Steel/Corrosion products + Bentonite/Water, was simulated and the corrosion behavior of the carbon steel in this state investigated. The following facts became apparent. Both the corrosion rate and the non-uniformity of it increased with increase in the corrosion product content in the compacted bentonite. When the corrosion product layer was formed between the carbon steel and the bentonite, it enabled the corrosion potential and increased the corrosion rate
Additional details
Publishing Information
- Publisher
- Materials Research Society.
- Imprint Place
- Pittsburgh, PA (United States)
- ISBN
- 1-55899-253-7
- Imprint Title
- Scientific basis for nuclear waste management 18. Part 1
- Imprint Pagination
- 787 p.
- Series
- Materials Research Society symposium proceedings, Volume 353.
- Journal Page Range
- p. 711-718.
Conference
- Title
- 18. international symposium on the scientific basis for nuclear waste management.
- Dates
- 23-27 Oct 1994.
- Place
- Kyoto (Japan).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28006110
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENTONITE; BUFFERS; CARBON STEELS; CONTAINERS; CORROSION; HIGH-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE FACILITIES; SERVICE LIFE; SIMULATION; UNDERGROUND DISPOSAL; WASTE-ROCK INTERACTIONS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CLAYS; INORGANIC ION EXCHANGERS; ION EXCHANGE MATERIALS; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; MANAGEMENT; MATERIALS; MINERALS; NUCLEAR FACILITIES; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SILICATE MINERALS; STEELS; TRANSITION ELEMENT ALLOYS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES
Optional Information
- Secondary number(s)
- CONF-941075--.