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Assessment of Steam Generator Tube Flaw Size and...
Journal article

Assessment of Steam Generator Tube Flaw Size and Leak Rate Models

Abstract

The Canadian Nuclear Safety Commission recently developed the CANTIA (CANDUTM Tube Inspection Assessment) methodology for probabilistic assessment of inspection strategies for steam generator (SG) tubes as a direct effect on the early detection and prevention of tube failure and primary-to-secondary leak of reactor coolant. In an effort to improve CANTIA, an SG tube integrity assessment code, a relevant survey of the literature on the discharge …

Authors

Revankar ST; Riznic JR

Journal

Nuclear Technology, Vol. 167, No. 1, pp. 157–168

Publisher

Taylor & Francis

Publication Date

July 2009

DOI

10.13182/nt09-a8859

ISSN

0029-5450