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Abstract

Disposal of vitrified high activity waste in properly selected deep geological formations absorbs most of present R & D and appears acceptable from a technical point of view. Concerning safety, much uncertainty exists in models and input data, though disposal projects under development appear to satisfy present radiological protection criteria. Among other disposal concepts studied with more limited efforts the following are briefly treated here: disposal in deep oceanic sediments; actinide separation and recycling; and: extraterrestrial disposal. These options should be considered as scientific research which may lead to industrial realization in a more mature nuclear age. Long-term storage of either spent fuel or vitrified waste, although not an alternative strategy of disposal, has considerable effects on waste management and the fuel cycle in general. The three scenarios (disposal of vitrified waste in geological formations, extended storage, advanced disposal options) complement each other very well and none of them should be pursued at the sacrifice of the others.

Additional information

Authors: GIRARDI F JRC ISPRA ESTAB. (ITALY), JRC ISPRA ESTAB. (ITALY)
Bibliographic Reference: THE DISPOSAL OF LONG-LIVED AND HIGHLY RADIOACTIVE WASTES, LONDON (UK), MAY 30-31, 1985 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 32145 ORA
Availability: Can be ordered online
Record Number: 1989124023400 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en
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