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