The properties of WWER-440 type reactor pressure vessel steels cut out from operated units

Authors
Korolev, Y Kryukov, A Nikolaev, Y Platonov, P Shtrombakh, Y Langer, R Leitz, C Rieg, C Nikolaev, V
Citation
Y. Korolev et al., The properties of WWER-440 type reactor pressure vessel steels cut out from operated units, NUCL ENG DE, 195(2), 2000, pp. 137-142
Citations number
3
Categorie Soggetti
Nuclear Emgineering
Journal title
NUCLEAR ENGINEERING AND DESIGN
ISSN journal
00295493 → ACNP
Volume
195
Issue
2
Year of publication
2000
Pages
137 - 142
Database
ISI
SICI code
0029-5493(200002)195:2<137:TPOWTR>2.0.ZU;2-U
Abstract
This paper presents the results of study on radiation degradation occurring in WWER-440 reactor pressure vessel (RPV) steel, using subsize impact spec imens (5 x 5 x 27.5 mm(3)). The results of testing trepans and templates cu t out from WWER-440 reactor pressure vessels are considered. Ductile-to-bri ttle transition temperatures DBTT) obtained using standard Charpy and subsi ze impact specimens are compared. The relation between these two values is established. (C) 2000 Elsevier Science S.A. All rights reserved.