Analysis of the factors that impact the reliability of high level waste canister materials
The analysis encompassed identification and analysis of potential threats to canister integrity arising in the course of waste solidification, interim storage at the fuels reprocessing plant, wet and dry shipment, and geologic storage. Fabrication techniques and quality assurance requirements necessary to insure optimum canister reliability were considered taking into account such factors as welding procedure, surface preparation, stress relief, remote weld closure, and inspection methods. Alternative canister materials and canister systems were also considered in terms of optimum reliability in the face of threats to the canister's integrity, ease of fabrication, inspection, handling and cost. If interim storage in air is admissible, the sequence suggested comprises producing a glass-type waste product in a continuous ceramic melter, pouring into a carbon steel or low-alloy steel canister of moderately heavy wall thickness, storing in air upright on a pad and surrounded by a concrete radiation shield, and thereafter placing in geologic storage without overpacking. Should the decision be to store in water during the interim period, then use of either a 304 L stainless steel canister overpacked with a solution-annealed and fast-cooled 304 L container, or a single high-alloy canister, is suggested. The high alloy may be Inconel 600, Incoloy Alloy 800, or Incoloy Alloy 825. In either case, it is suggested that the container be overpacked with a moderately heavy wall carbon steel or low-alloy steel cask for geologic storage to ensure ready retrievability. 19 figs., 5 tables.
- Research Organization:
- Battelle Columbus Labs., OH (USA)
- DOE Contract Number:
- EY-77-C-06-1030
- OSTI ID:
- 6703188
- Report Number(s):
- RHO-C-7
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
052000* -- Nuclear Fuels-- Waste Management
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CALCINATION
CHEMICAL REACTIONS
CONTAINERS
CRYSTALLIZATION
DECOMPOSITION
FABRICATION
HIGH-LEVEL RADIOACTIVE WASTES
MANAGEMENT
MELTING
PHASE TRANSFORMATIONS
PROCESSING
PYROLYSIS
QUALITY ASSURANCE
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
RADIOACTIVE WASTES
RECOMMENDATIONS
RELIABILITY
SOLIDIFICATION
STORAGE
THERMOCHEMICAL PROCESSES
TRANSPORT
UNDERGROUND STORAGE
VITRIFICATION
WASTE MANAGEMENT
WASTE PROCESSING
WASTE STORAGE
WASTES
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CALCINATION
CHEMICAL REACTIONS
CONTAINERS
CRYSTALLIZATION
DECOMPOSITION
FABRICATION
HIGH-LEVEL RADIOACTIVE WASTES
MANAGEMENT
MELTING
PHASE TRANSFORMATIONS
PROCESSING
PYROLYSIS
QUALITY ASSURANCE
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
RADIOACTIVE WASTES
RECOMMENDATIONS
RELIABILITY
SOLIDIFICATION
STORAGE
THERMOCHEMICAL PROCESSES
TRANSPORT
UNDERGROUND STORAGE
VITRIFICATION
WASTE MANAGEMENT
WASTE PROCESSING
WASTE STORAGE
WASTES