Title of article
The properties of WWER-440 type reactor pressure vessel steels cut out from operated units Original Research Article
Author/Authors
Y. Korolev، نويسنده , , A. Kryukov، نويسنده , , Nikolay Y. Nikolaev، نويسنده , , P. Platonov، نويسنده , , Y. Shtrombakh، نويسنده , , R. Langer، نويسنده , , C. Leitz، نويسنده , , C.Y. Rieg، نويسنده , , V. Nikolaev، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 1999
Pages
6
From page
137
To page
142
Abstract
This paper presents the results of study on radiation degradation occurring in WWER-440 reactor pressure vessel (RPV) steel, using subsize impact specimens (5×5×27.5 mm3). 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.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
1999
Journal title
Nuclear Engineering and Design Eslah
Record number
889038
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