Hydrogen resistance of Ni base alloys under stress corrosion and fatigue corrosion
Creators
- 1. Ecole Nationale Superieure des Mines, 42 - Saint-Etienne (France)
Description
One of the major problem for steam generator tubes in Pressurized Water Reactor (PWR) is the resistance of Ni base alloys to Stress Corrosion Cracking (SCC) and Corrosion Fatigue (CF). Previous studies of mechanisms involve the effect of hydrogen on the damage process together with segregation of impurities. It bas been shown that a galvanic cell may be established, in the power plant, upon contact due to the fact that the Ni base alloy is cathodic relative to the carbon steel support plate. Thus the aim of this research is to analyse the effect of hydrogen on the Ni base alloy fatigue behaviour, through CF tests in a 0.5 N H2SO4 solution at cathodic and free potentials in comparison to tests in air. These tests are performed on Ultra High Purity (UHP) Ni and Ni base alloys (corresponding to the FCC matrix of Inconel 600 and Inconel 690) to avoid the effect of impurities, such as sulphur, on localized corrosion and grain boundary (GB) embrittlement (S, 0, C, N < 10 ppm). Localized corrosion-deformation interactions are taken into account through the relation between cyclic plasticity, strain localization and hydrogen absorption. A particular attention is paid on the Persistent Slip Bands (PSB)-GB interactions in relation with hydrogen effects. (authors). 6 refs., 2 figs
Additional details
Publishing Information
- Publisher
- Ecole Nationale Superieure des Mines.
- Imprint Place
- Saint-Etienne (France)
- Imprint Title
- Super Alloys
- Imprint Pagination
- 100 p.
- Journal Page Range
- p. 20.1-20.4.
Conference
- Title
- 35. Meeting of Cercle d'Etudes des Metaux.
- Dates
- 24-25 Apr 1996.
- Place
- Saint-Etienne (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 28017356
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUSTENITIC STEELS; BWR TYPE REACTORS; CORROSION FATIGUE; CORROSION RESISTANT ALLOYS; CRACKS; HEAT RESISTING ALLOYS; HYDROGEN; INCONEL 600; INCONEL 690; MECHANICAL PROPERTIES; NICKEL BASE ALLOYS; PWR TYPE REACTORS; REFRACTORIES; STAINLESS STEELS; STRESS CORROSION; SURFACE PROPERTIES; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- ALLOY-NI59CR30FE9; ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION; ELEMENTS; ENRICHED URANIUM REACTORS; FATIGUE; HEAT RESISTANT MATERIALS; HIGH ALLOY STEELS; INCONEL ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; NICKEL ALLOYS; NIMONIC; NONMETALS; POWER REACTORS; REACTORS; STEELS; TEMPERATURE RANGE; THERMAL REACTORS; TITANIUM ADDITIONS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS