Materials performance in nuclear pressurized water reactor steam generators
Conference
·
· Nucl. Technol.; (United States)
OSTI ID:5198244
The nuclear industry has had a variety of reliability problems with pressurized water reactor steam generators. Most of these problems have been associated with corrosion and mechanically induced damage, including secondary water intergranular corrosion and stress corrosion cracking (SCC), primary water SCC, wastage, high cycle fatigue, and fretting and wear of the Inconel 600 or Incoloy 800 tubes, plus accelerated corrosion of carbon steel tube support structures in crevice regions. This article discusses steam generator material performance. 23 refs.
- Research Organization:
- EPRI, Palo Alto, Calif, USA
- OSTI ID:
- 5198244
- Report Number(s):
- CONF-801036-
- Conference Information:
- Journal Name: Nucl. Technol.; (United States) Journal Volume: 55:1
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BOILERS
CHEMICAL REACTIONS
CORROSION
DAMAGE
MATERIALS TESTING
PWR TYPE REACTORS
REACTORS
STEAM GENERATORS
TESTING
TUBES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BOILERS
CHEMICAL REACTIONS
CORROSION
DAMAGE
MATERIALS TESTING
PWR TYPE REACTORS
REACTORS
STEAM GENERATORS
TESTING
TUBES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS