Title of article
Failure assessment of RPV nozzle under loss of coolant accident
Author/Authors
Nagel، G. نويسنده , , Hodulak، L. نويسنده , , Siegele، D. نويسنده , , Varfolomeyev، I. نويسنده ,
Issue Information
دوهفته نامه با شماره پیاپی سال 1999
Pages
-264
From page
265
To page
0
Abstract
In case of a postulated loss of coolant accident (LOCA) of a reactor pressure vessel (RPV), the nozzle region experiences higher stresses and lower temperatures than the remaining part of the RPV. Thus, the nozzle is to be considered in the RPV safety assessment. For a LOCA event, three-dimensional elastic-plastic finite element calculations of stresses and strains in the intact RPV were performed. Using the substructure technique, fracture mechanics analyses were then carried out for several postulated cracks in the nozzle corner and in the circumferential weld below the nozzle. For different crack geometries and locations, the J-integral and the stress intensity factor were calculated as functions of the crack tip temperature. Based on the .K ic-reference curve and the J R curve, both brittle and ductile instability of the postulated cracks were excluded. In order to reduce the expenses of three-dimensional finite element analyses for various crack geometries, an analytical procedure for calculating stress intensity factors of subclad cracks in cylindrical components was extended for cracks in the nozzle corner. © 1999 Elsevier Science S.A. All rights reserved.
Keywords
Transient data collection , Fatigue monitoring , Pressurized water reactors
Journal title
Nuclear Engineering and Design
Serial Year
1999
Journal title
Nuclear Engineering and Design
Record number
14290
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