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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