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
Link To Document :
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