Parametric calculations of fatigue-crack growth in piping. [PWR; BWR]

Conference · Wed Jun 01 04:00:00 EDT 1983

OSTI ID:5874523

Simonen, F A; Goodrich, C W

This study presents calculations of the growth of piping flaws produced by fatigue. Flaw growth was predicted as a function of the initial flaw size, the level and number of stress cycles, the piping material, and environmental factors. The results indicate that the present flaw acceptance standards of ASME Section XI provide a relatively consistent set of allowable flaw sizes because the predicted life of flawed piping is relatively insensitive to pipe wall thickness, flaw aspect ratio, and piping material (ferritic versus austenitic). On the other hand, the results show that flaws that are acceptable under ASME Section XI can grow at unacceptable rates if the cyclic stresses are at the maximum level permitted by the design rules of ASME Section III. However, a review of the conservatisms inherent to the ASME code rules is presented to explain the low occurrence of piping fatigue failures in service. It is concluded that decreases in the allowable flaw sizes are not justified.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5874523
• Report Number(s): PNL-SA-11134; CONF-830607-24; ON: DE83013827
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ALLOYS
BWR TYPE REACTORS
CRACKS
DEFECTS
FAILURES
FATIGUE
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
PIPES
PWR TYPE REACTORS
REACTORS
STEELS
WATER COOLED REACTORS
WATER MODERATED REACTORS