Survey of VVER reactors with a view to decommissioning requirementsFunded under: FP2-DECOM 3C
In order to determine the future CEC R&D efforts on decommissioning of nuclear facilities, it was considered relevant to scope the requirements in East Europe. After performing an inventory of East European nuclear facilities, the Russian pressurised water reactor, VVER-230 type, was selected as reference plant. This was mainly for the following reasons: plants exist in many East European countries; it is the oldest power reactor design; a decommissioning project on this design is starting now in Greifswald (Germany). In general, existing Western technologies and procedures developed for the decommissioning of nuclear power plants can be applied to the decommissioning of East European power plants. However, it is shown in this study that there are certain areas and specific subjects which need further development or adaptation before application. Examples can be found in the remote dismantling, handling and treatment of operational wastes as well as the dismantling procedure of the controlled area. Proposals are finally made for further activities, on a larger scale, eventually with the use of the Greifswald plant as a pilot project, and on a smaller scale using parts of the Greifswald plant as test object. However, before initiating larger projects, it is necessary to investigate the national situation, especially in relation to licensing practices, the existence of final storages, possibilities for fuel treatment, and financing aspects.
Bibliographic Reference: EUR 16549 EN (1995) 128 pp., FS, ECU 15
ISBN: ISBN 92-827-4673-9
Record Number: 199511394 / Last updated on: 1995-10-31
Original language: en
Available languages: en