Title of article :
Effect of cladding on the stress intensity factors in the reactor pressure vessel Original Research Article
Author/Authors :
S.N. Choi، نويسنده , , K.S. Jang، نويسنده , , J.S. Kim، نويسنده , , J.B. Choi، نويسنده , , Y.J. Kim، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2000
Pages :
11
From page :
101
To page :
111
Abstract :
In general, reactor pressure vessels (RPV) are cladded with stainless steel to prevent corrosion and radiation embrittlement. The ASME Sec. XI specifies that a subclad crack which may be found during the in-service inspection must be considered as a semi-elliptical surface crack when the thickness of cladding is less than 40% of the crack depth. In order to refine the fracture assessment procedures for such subclad cracks, three-dimensional finite element analyses were applied for various subclad cracks embedded in the base metal. A total of 18 crack geometries were analyzed, and the results were compared with those for idealized semi-elliptical surface cracks for two different loading conditions, i.e. internal pressure and pressurized thermal shock. The resulting stress intensity factors for subclad cracks were 50–70% less than those for idealized surface cracks. It has been proven that the condition specified on the ASME Sec. XI is overly conservative for subclad cracks which are assumed to be surface cracks.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2000
Journal title :
Nuclear Engineering and Design Eslah
Record number :
889146
Link To Document :
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