Community Research and Development Information Service - CORDIS

Abstract

Within the framework of the R&D programme on Management and Storage of Radioactive Waste of the European Atomic Energy Community, one project is dedicated to the development of containers for vitrified high level waste to be disposed of in geological formations. In particular, a joint testing programme has been established for the assessment of the corrosion behaviour of potential materials in the different disposal environments considered, respectively granite, salt and clay. As a result of previous screening tests on a number of materials, a detailed testing programme is presently concentrated on three most promising reference materials, respectively Hastelloy C4, Ti-Pd (0.2 % Pd) and a mild steel.

Additional information

Authors: HAIJTINK B CEC BRUXELLES (BELGIUM) ACCARY A UNIVERSITY OF CLERMONT-FERRANT II (FRANCE) , CEC BRUXELLES (BELGIUM);UNIVERSITY OF CLERMONT-FERRANT II (FRANCE)
Bibliographic Reference: WASTE MANAGEMENT 1984, TUCSON, ARIZONA (USA), MARCH 11-15, 1984 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 31429 ORA
Availability: Can be ordered online
Record Number: 1989122073100 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en