Assessment of Crack Leak Rate for Inspection Strategies for Steam Generator Tubes
Brian Wolf1,a, Shripad T. Revankar1,b and Jovica R. Riznic2
1Purdue University, West Lafayette, IN 47907, USA.
awolfb@purdue.edu
bshripad@ecn.purdue.edu
2Canadian Nuclear Safety Commission, Ottawa, Ontario, K1P 5S9, Canada.
jovica.riznic@cnsc-ccsn.gc.ca
ABSTRACT
The Canadian Nuclear Safety Commission (CNSC) recently developed the CANTIA methodology for probabilistic assessment of inspection strategies for steam generator tubes as a direct effect on the probability of tube failure and primary-to-secondary leak rate. One of the important topic in the assessment is the crack growth model that predicts the growth of crack size with time. The ANL/CANTIA code predictions were systematically studied to evaluate the code capability to predict the leak rates through the flawed steam generator tubes. In this evaluation the code models on the crack opening area, the probabilistic models and the critical flow rate models were studied and their applicability to available experimental data base was examined.
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