The relationship between observed stress corrosion cracking fracture morphology and microstructure in Alloy 600
- Bettis Atomic Power Lab., West Mifflin, PA (United States)
- Westinghouse Electric Corp., Pittsburgh, PA (United States). Westinghouse Science and Technology Center
Microstructure is known to influence the stress corrosion cracking (SCC) behavior of Alloy 600 in both hydrogenated water and steam environments. This study evaluated the relative SCC response of a single heat of Alloy 600 as a function of microstructure in a hydrogenated doped-steam environment. The 400 C doped-steam environment was selected for the SCC tests to accelerate cracking. The material was evaluated in three conditions: (1) as-received (2) as-annealed, and (3) as-annealed + 26% deformation. Microstructural characterization was performed using analytical electron microscopy (AEM) techniques for the evaluation of carbide type and morphology, and general structure. Constant displacement (bolt-loaded) compact tension specimens were used to induce SCC. The as-annealed and as-annealed plus cold worked samples had two fracture morphologies: a rough intergranular SCC fracture morphology and a smooth intergranular fracture morphology. The SCC fracture in the as-received specimens was characterized by a classic intergranular morphology at low magnification, consistent with the microstructural evaluation of cross-sectional metallographic samples. More detailed examination revealed a pseudo-intergranular fracture morphology. This pseudo-intergranular morphology appears to be comprised of very fine cleavage-like microfacets. These observations may assist in understanding the difference in SCC fracture morphologies as reported in the open literature.
- Research Organization:
- Bettis Atomic Power Lab., West Mifflin, PA (United States)
- Sponsoring Organization:
- USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
- DOE Contract Number:
- AC11-93PN38195
- OSTI ID:
- 291121
- Report Number(s):
- WAPD-T-3130; CONF-970832-; ON: DE99000483; TRN: 99:002314
- Resource Relation:
- Conference: 8. international symposium on environmental degradation of materials in nuclear power systems-water reactors, Amelia Island, FL (United States), 10-14 Aug 1997; Other Information: PBD: [1997]
- Country of Publication:
- United States
- Language:
- English
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