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Abstract

This work was performed within the activity of the third Programme of the European Community on the decommissioning of nuclear installations. Its first aim is the study and development of chemical processes, at a laboratory scale, in order to treat properly the radioactive graphite originating in nuclear installations, and to dispose of it adequately. The project includes four tasks: to characterise the graphite, to isolate the radionuclides, to waterproof the graphite by utilising metal covering materials, and to study the process of leaching. The isotopic content of the radioactive graphite, the original of the radionuclides, its localisation inside the graphite itself, and its possible escape, as a form of gas or through a process of leaching, have been studied.

Additional information

Authors: ESTEBAN-DUQUE A, CIEMAT, Madrid (ES);ROMERO N, CIEMAT, Madrid (ES);FABRELLAS B, CIEMAT, Madrid (ES);RODRÍGUEZ F, Universidad de Alicante, Departamento de Química Inorgánica e Ingeniería Química (ES);MOLINA M, Universidad de Alicante, Departamento de Química Inorgánica e Ingeniería Química (ES);CATURLA F, Universidad de Alicante, Departamento de Química Inorgánica e Ingeniería Química (ES);MOLINA F, Universidad de Alicante, Departamento de Química Inorgánica e Ingeniería Química (ES);RODRIGUEZ F, Universidad de Alicante, Departamento de Quimica Inorganica e Ingenieria Quimica (ES)
Bibliographic Reference: EUR 16767 ES (1996) 178pp., FS, ECU 20
Availability: Available from the (2)
ISBN: ISBN 92-827-6118-5
Record Number: 199710466 / Last updated on: 1997-05-09
Category: PUBLICATION
Original language: es
Available languages: es
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