Title of article :
Behaviour of a PWR vessel dissimilar metal weld during a steam line break transient
Author/Authors :
Bhandari، S. نويسنده , , Dubois، D. نويسنده , , Guichard، D. نويسنده ,
Issue Information :
دوهفته نامه با شماره پیاپی سال 2001
Pages :
-326
From page :
327
To page :
0
Abstract :
This paper presents the results of a Finite Element analysis conducted on the behaviour of a 15 mm deep fully circumferential crack on the outer surface of a bi-metallic weld of a 900 MWe Pressurized Water Reactor vessel, during a Steam Line Break transient. The typical weld considered connects the stainless-steel hot leg with the ferritic vessel. This work is part of a Benchmark exercise organised in the framework of an European Commission (DG Environment) project on Transition Welds. However, the results presented here concern only those obtained at Framatome using SYSTUS + code and deal with the thermo-mechanical analysis, the evaluation of the crack driving energy (J-integral) and a discussion on crack stability. These results are compared with those obtained using a simplified method developed earlier and presented at one of the international conferences.
Keywords :
Plant life management , Power plants , Power stations
Journal title :
Nuclear Engineering and Design
Serial Year :
2001
Journal title :
Nuclear Engineering and Design
Record number :
13697
Link To Document :
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