Community Research and Development Information Service - CORDIS

Abstract

This paper focuses on the material properties of WWER 440 reactors. The lack of material data is a real problem of the 230 model reactors and the high lead factor in the surveillance irradiations of the more modern 213 units is a considerable uncertainty in a safety assessment of the units. In addition, most of the 230 units have been, and some of the 213 units will be, annealed. Griefswald units are fully representative WWER 440 units and they offer examples of irradiated, irradiated-annealed and irradiated-annealed-reirradiated blocks. In this paper a basic material research programme is proposed, which can greatly support the operating WWER units.

Additional information

Authors: VALO M, VTT Manufacturing Technology (FI);TÖRRÖNEN K, VTT Manufacturing Technology (FI);BÖHMERT J, Research Centre Rossendorf, Institute for Safety Research, Dresden (DE);VON ESTORFF U, JRC Petten (NL)
Bibliographic Reference: Paper presented: International Workshop on Aged and Decommissioned Material Collection, Keel (BE), June 27-28, 1995
Availability: Available from (1) as Paper EN 39191 ORA
Record Number: 199511354 / Last updated on: 1995-10-31
Category: PUBLICATION
Original language: en
Available languages: en