Stress analysis of pressurized water reactor steam generator tube denting phenomena. Interim report
In some Pressurized Water Reactor (PWR) steam generators, a corrosion product has formed on the carbon steel support plate in the crevice between the tube and support plate. The corrosion product occupies more volume than the original metal; the tube-to-support plate crevice volume is thus consumed with corrosion product, and further corrosive action results in a radially inward force on the tube and a radially outward force on the corroding support plate. This has resulted in indentation (''denting'') of the tube, accompanied by occasional cracking. Large in-plane deformation and cracking of support plates has also been observed in the most severely affected plants along with some serious side effects, such as deformation and cracking of inner row tube U-bends caused by support plate movement. Mechanical aspects of the tube denting phenomena have been studied using analytical models. The models used ranged from closed form analytical solutions to state-of-the-art numerical elastic-plastic computer program for moderate strains. It was found that tube dents, such as those observed in operating steam generators, are associated with yielding of both the tubes and support plates. Also studied were the stresses in tube U-bends caused by support plate flow slot deformation.
- Research Organization:
- Failure Analysis Associates, Palo Alto, CA (USA)
- OSTI ID:
- 6803020
- Report Number(s):
- EPRI-NP-828; TRN: 78-019638
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
PWR TYPE REACTORS
STEAM GENERATORS
STRESS ANALYSIS
CORROSION
CORROSION PRODUCTS
DEFORMATION
TUBES
BOILERS
CHEMICAL REACTIONS
REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled