SYMPOSIA PAPER Published: 01 January 1993

Evaluation of the Recovery Annealing of the Reactor Pressure Vessel of NPP Nord (Greifswald) Units 1 and 2 by Means of Subsize Impact Specimens


In 1988 and 1990, the reactor pressure vessels of Units 1 and 2, respectively, of the Greifswald nuclear power station were subjected to heat treatment at 475°C for annealing of irradiation effects. To demonstrate the effect of annealing and to evaluate a new postannealing transition temperature of vessel base metal and weld metal, boat samples were removed by means of electric discharge machining (EDM) from the (unclad) inner surface of the vessel. From these samples, micronotched bar impact test specimens were fabricated and tested at different temperatures. Transition curves were evaluated from the results. By means of correlation tests, the transition temperatures evaluated from the micro-specimen tests are converted to standard Charpy-V transition temperatures. Results are available for the weld metal of Unit 1 after annealing. The transition temperature TK is lower than the value calculated by the designer of the plant. Specimens removed from Unit 2 before and after annealing are in preparation.

Author Information

Ahlstrand, R
Imatra Power Company (IVO), Vantaa, Finland
Klausnitzer, EN
Siemens AG, Power Generation Group, KWU, Erlangen, Germany
Lange, D
Energiewerke Nord AG, Greifswald, Germany
Leitz, C
Siemens AG, Power Generation Group, KWU, Erlangen, Germany
Pastor, D
Energiewerke Nord AG, Greifswald, Germany
Valo, M
Technical Research Centre (VTT), Espoo, Finland
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Developed by Committee: E10
Pages: 321–343
DOI: 10.1520/STP24785S
ISBN-EB: 978-0-8031-5228-1
ISBN-13: 978-0-8031-1478-4