SYMPOSIA PAPER Published: 01 January 1998
STP37989S

The Actual Properties of WWER-440 Reactor Pressure Vessel Materials Obtained by Impact Tests of Subsize Specimens Fabricated out of Samples Taken from the RPV

Source

This paper presents the results of a study on degradation due to irradiation occurring in WWER-440 reactor pressure vessel (RPV) steel, using subsize Charpy specimens (5×5×27.5 mm3). An application of subsize specimens for estimation of irradiation embrittlement of RPV steel has been substantiated. Comparison between ductile-to-brittle transition temperatures (DBTT) for full-size and subsize Charpy specimens has been carried out. The relation between these two values has been clarified. The results of testing trepans and templates cut out from WWER-440 reactor pressure vessels are considered. The main results of the program TACIS-91/1.1. are discussed.

Author Information

Korolev, YN
ORM Russian Research Center “Kurchatov Institute”, Moscow, Russia
Kryukov, AM
ORM Russian Research Center “Kurchatov Institute”, Moscow, Russia
Nikolaev, YA
ORM Russian Research Center “Kurchatov Institute”, Moscow, Russia
Platonov, PA
ORM Russian Research Center “Kurchatov Institute”, Moscow, Russia
Shtrombakh, YI
ORM Russian Research Center “Kurchatov Institute”, Moscow, Russia
Langer, R
Siemens AG KWU NT13, Erlangen, Germany
Leitz, C
Siemens AG KWU NT13, Erlangen, Germany
Rieg, C-Y
Immeuble France-Evry-Boukvard France — BP.128, France
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Details
Developed by Committee: E10
Pages: 145–159
DOI: 10.1520/STP37989S
ISBN-EB: 978-0-8031-5565-7
ISBN-13: 978-0-8031-2476-9