Grain boundary microstructure, chemistry, and IGSCC in Alloy 600 and Alloy 690

Conference · Thu Dec 31 00:00:00 EST 1992

OSTI ID:48082

Norring, K ^[1]; Stiller, K ^[2]; Nilsson, J O ^[3]

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1. Studsvik AB, Nykoeping (Sweden)
2. Chalmers Univ. of Technology, Goeteborg (Sweden)
3. AB Sandvik Steel, Sandviken (Sweden)

The resistance to intergranular stress corrosion cracking of six different Alloy 600 and Alloy 690 steam generator tubes has been investigated. The composition of the materials at grain boundaries has been investigated using analytical transmission electron microscopy and atom probe field ion microscopy techniques. The depletion of chromium at the grain boundaries has been related to the type of grain boundary precipitates. Segregation of carbon and boron to the grain boundaries has been observed and quantified.

• OSTI ID: 48082
• Report Number(s): CONF-910808-; TRN: 95:011513
• Resource Relation: Conference: 5. international symposium on environmental degradation of materials in nuclear power systems - water reactors, Monterey, CA (United States), 25-29 Aug 1991; Other Information: PBD: 1992; Related Information: Is Part Of Proceedings of the fifth international symposium on environmental degradation of materials in nuclear power systems - water reactors; PB: 995 p.
• Country of Publication: United States
• Language: English

Related Subjects

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
INCONEL 600
STRESS CORROSION
INTERGRANULAR CORROSION
INCONEL 690
TUBES
STEAM GENERATORS
PWR TYPE REACTORS