Community Research and Development Information Service - CORDIS

Abstract

The requirements and design features have been studied for containers to isolate vitrified high level radioactive waste for 500 to 1 000 years. The requirements for handling, storing and transporting containers have been identified, and the pressures and temperatures possibly experienced in clay, granite and salt formations estimated. A range of possible container designs have been proposed for each of the disposal environments. Alternative design concepts in corrosion resistant or corrosion allowance material have been suggested. (Some resist pressure by using a structural shell). Potentially suitable container shell materials: metals have not been specified in detail, but titanium alloys and low carbon steels may be appropriate for corrosion resistant and corrosion allowance designs respectively. Performance requirements for container filler materials have been identified and candidate materials assessed. No entirely suitable materials have been found as yet. A preliminary container stress analysis has shown the importance of thermal modelling and: lead used as a filler dominates the stress response of the container. Possible methods of manufacturing disposal containers have been assessed and found to be generally feasible although filling operations and container closure could be difficult.

Additional information

Authors: OVE ARUP & PARTNERS OVE ARUP & PARTNERS, LONDON (UK), OVE ARUP & PARTNERS, LONDON (UK)
Bibliographic Reference: EUR 9909 EN (1985) FS, 148 P., BFR 500, EUROFFICE, LUXEMBOURG, POB 1003
Availability: Can be ordered online
Record Number: 1989124008600 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en