Steam generator tube integrity program: Phase II, Final report
The Steam Generator Tube Integrity Program (SGTIP) was a three phase program conducted for the US Nuclear Regulatory Commission (NRC) by Pacific Northwest Laboratory (PNL). The first phase involved burst and collapse testing of typical steam generator tubing with machined defects. The second phase of the SGTIP continued the integrity testing work of Phase I, but tube specimens were degraded by chemical means rather than machining methods. The third phase of the program used a removed-from-service steam generator as a test bed for investigating the reliability and effectiveness of in-service nondestructive eddy-current inspection methods and as a source of service degraded tubes for validating the Phase I and Phase II data on tube integrity. This report describes the results of Phase II of the SGTIP. The object of this effort included burst and collapse testing of chemically defected pressurized water reactor (PWR) steam generator tubing to validate empirical equations of remaining tube integrity developed during Phase I. Three types of defect geometries were investigated: stress corrosion cracking (SCC), uniform thinning and elliptical wastage. In addition, a review of the publicly available leak rate data for steam generator tubes with axial and circumferential SCC and a comparison with an analytical leak rate model is presented. Lastly, nondestructive eddy-current (EC) measurements to determine accuracy of defect depth sizing using conventional and alternate standards is described. To supplement the laboratory EC data and obtain an estimate of EC capability to detect and size SCC, a mini-round robin test utilizing several firms that routinely perform in-service inspections was conducted.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 7119378
- Report Number(s):
- NUREG/CR-2336; PNL-4008; ON: TI88015389
- Country of Publication:
- United States
- Language:
- English
Similar Records
Steam generator group project: Task 13 final report: Nondestructive examination validation
1984 NRC Branch annual report: Steam Generator Group Project
Related Subjects
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BOILERS
CHEMICAL REACTIONS
CORROSION
CRACKS
DOCUMENT TYPES
EDDY CURRENT TESTING
ELECTROMAGNETIC TESTING
FAILURES
FLUID MECHANICS
LEAKS
MATERIALS TESTING
MECHANICS
NONDESTRUCTIVE TESTING
PROGRESS REPORT
PWR TYPE REACTORS
REACTORS
RELIABILITY
RUPTURES
STEAM GENERATORS
STRESS CORROSION
TESTING
TUBES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS