ANL/CANTIA: A Computer Code for Steam Generator Integrity Assessments (NUREG/CR-6786)

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Publication Information

Manuscript Completed: December 2001
Date Published: September 2002

Prepared by:
S. Majumdar

Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439

J. Davis, NRC Project Manager

Prepared for:
Division of Engineering Technology
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

NRC Job Code W6822

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Abstract

This report summarizes the work carried out to modify and expand the capability of the steam generator integrity code CANTIA originally developed for CANDU reactors. The basic algorithms for the Monte Carlo simulation, the random initiation of cracks, the effect of inservice inspection including the probability of detection (POD) of cracks, and the inclusion of plugging criteria for defective tubes have been retained. Additional ligament rupture, unstable burst, and leak rate models for Alloy 600 tubes that have been developed or validated at Argonne National Laboratory have been incorporated into the code. Fracture mechanics models for crack growth rate based on stress corrosion cracking data from the literature have also been added. The basic treatment of flaw growth has been changed from one- to two-dimensional, and crack growth calculations have been made more rigorous.