Title of article
The properties of WWER-440 type reactor pressure vessel steels cut out from operated units
Author/Authors
Korolev، Y. نويسنده , , Kryukov، A. نويسنده , , Nikolaev، Y. نويسنده , , Platonov، P. نويسنده , , Shtrombakh، Y. نويسنده , , Langer، R. نويسنده , , Leitz، C. نويسنده , , Ricg، C.Y. نويسنده , , Nikolaev، V. نويسنده ,
Issue Information
دوهفته نامه با شماره پیاپی سال 2000
Pages
-136
From page
137
To page
0
Abstract
This paper presents the results of study on radiation degradation occurring in WWER-440 reactor pressure vessel (RPV) steel, using subside impact specimens (5 *5 * 27.5 mm^3). The results of testing trepans and templates cut out from WWER-440 reactor pressure vessels are considered. Ductile-to-brittle transition temperatures (DBTT) obtained using standard Charpy and subsize impact specimens are compared. The relation between these two values is established.
Keywords
Participation , Problem solving , Production , Change , Renewal , Working conditions
Journal title
Nuclear Engineering and Design
Serial Year
2000
Journal title
Nuclear Engineering and Design
Record number
13682
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