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Abstract

The preferred solution that emerged from this study was for a concrete semi-submersible platform to be maintained in position by a dynamic positioning station keeping system. The radioactive waste would be carried out to the platform contained in transfer flasks and loaded onto the platform. There, inside a flooded compartment, the flasks would be opened and the canisters lifted out and formed into strings which would then be lowered to the sea bed using drill pipe and guided into the previously drilled hole. Most of the operations for emplacing the waste are either within the bounds of existing technology or are within foreseeable development. However, there remain considerable difficulties in recovering from various malfunctions, in particular a dropped string of canisters. Disposal of 400 m**3 per year is within the capacity of a single offshore platform, though certain restrictions on the operation may be necessary if the waste is in the small diameter (300 mm) form. The cost of disposal of waste by this means would add about 0.2 % to the cost of generation. The costs of disposal are not excessive and should not, therefore, be a deterrent from choosing this system if it should prove to be more reliable than any other system.

Additional information

Authors: BURY M R C TAYLOR WOODROW CONSTRUCTION LIMITED, SOUTHALL, MIDDLESEX (UK), TAYLOR WOODROW CONSTRUCTION LIMITED, SOUTHALL, MIDDLESEX (UK)
Bibliographic Reference: 184 P., 1985, ISBN 0 860 10 708 6 WRITE TO GRAHAM & TROTMAN LTD., 66 WILTON ROAD, LONDON SW1V 1DE (UK), PRICE: UKL 30,-, (EUR 9754 EN).
Record Number: 1989123062100 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en
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