Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Advances in flaw evaluation procedures and acceptance criteria for reactor piping

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6499113
During the past several years, intergranular stress corrosion cracks (IGSCC) have been detected in stainless steel piping in boiling water reactors (BWRs) and have resulted in an increased number of flaw evaluations. To reduce the outage time associated with evaluating IGSCC, various research and ASME code groups have spent significant effort to provide utility personnel with efficient means to detect, classify, and size flaws, and to determine suitability for return to service for flawed stainless steel piping. One of the several nondestructive evaluation technologies that has received considerable attention is fracture mechanics, the discipline that considers the failure of flawed material. Fracture mechanics can be used to answer two key questions concerning return to service of flawed pipe: (a) what is the largest flaw size that can be returned to service and still maintain adequate safety margins at the applied loads, and (b) how much operating time remains before the crack reaches the largest allowable size. The purpose of this paper is to provide an overview of the recently developed ASME code Section XI flaw size evaluation procedure and acceptance criteria for stainless steel piping and their application by BWR owners to efficiently determine if flaws found by nondestructive examination are acceptable for continued service.
Research Organization:
NOVETECH Corp., Rockville, MD
OSTI ID:
6499113
Report Number(s):
CONF-860610-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
Country of Publication:
United States
Language:
English