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Abstract

In this paper the main results obtained in the framework of Phare project 4.1.2/93 are discussed. The main objective of this project was to propose measures to increase the effectiveness of in-service inspection (ISI) of VVER 440 and 1000 reactor pressure vessel components. An analysis was made of all existing information in order to identify these components of the reactor pressure vessels for which the ISI effectiveness should be verified and increased. Different damage mechanisms were identified and were classified in 2 categories: specific (well known) and postulated. A structural integrity assessment was done in order to define the critical defect sizes. 3 test qualification test pieces were manufactured covering the following areas: the VVER 440-213 nozzle inner radius, the VVER 440-213 dissimilar metal weld, the VVER 1000-320 nozzle inner radius and the VVER 1000-320 homogeneous weld. The following defect types were considered: fatigue cracks, underclad cracks and lack of fusion defects.

Additional information

Authors: LIÉTARD J P, Belgatom, Bruxelles (BE);HEUMULLER R, Siemens AG, Erlangen (DE);ENCRENAZ P, Intercontrôle, Rungis (FR);HORACEK L, Nuclear Research Institute Rez (CZ);CHAMPIGNY F, Electricité de France, Production Transport, Saint-Denis (FR);LEMAITRE P, JRC Petten (NL)
Bibliographic Reference: Paper presented: ICONE-6, San Diego (US), May 10-15, 1998
Availability: Available from (1) as Paper EN 41774 ORA
Record Number: 199811391 / Last updated on: 1998-11-10
Category: PUBLICATION
Original language: en
Available languages: en