Crack growth rates in thick materials of alloy 600 and weld metals of alloy 182 in laboratory primary water comparison with field Experience
- 1. Electricite de France (EDF), 75 - Paris (France). Region d'Equipement
- 2. Electricite de France (EDF), DIS/SEPTEN, 75 - Paris (France)
- 3. CEA Saclay, Dept. de Physico-Chimie DPC/SCCME, 91 - Gif sur Yvette (France)
Description
Since 1991, when a first leakage occurred on the vessel head of Bugey 3 RPV, an important investigation program was undertaken in laboratory in order to assess crack growth rates (CGRs) of vessel head penetrations (VHPs) in alloy 600 and weld metal in alloy 182 in primary environments. SCC (stress corrosion cracking) tests were performed between 290 C and 360 C on pre-cracked specimens under static loading. Alloy 600: On VHPs with YS20 ranging from 300 MPa to 468 MPa, it was found that the upper bound for CGRs were dependant on (K(T initial)-K(iscc))0.3, in accordance with field experience. In laboratory condition, the activation energy was 130 ± 20 kJ/mol, the yield stress increased significantly CGRs but some coupling effects were noted with the microstructure. Cold work increased slightly CGRs on a VHP with initial YS = 468 MPa. Additional tests were performed at 290 C and 325 C on rolled bars, rolled plates and forged plates representative of the other components in alloy 600 of the primary circuit: products with low YS and high GBC had low sensitivity to SCC but it could be significantly increased with cold work raising at the level of 468 MPa, the highest YS investigated on VHPs. Stress relief treatment did not significantly modify SCC resistance. On ten products from the various components, the measured CGRs were strongly correlated to the material susceptibility index for SCC initiation. Alloy 182: Some comparisons were performed in laboratory, with different orientations. Similar trends to alloy 600 were found for the influences of K and temperature on CGRs. 10% cold work increased and stress relief treatment decreased CGRs by a factor 2. CGRs of cracks propagating in the direction of dendrites were 2 to 5 times higher than for cracks propagating in the perpendicular direction. For both alloys 600 and 182, a model is proposed to account for the effects of the main parameters on CGRs and the relevance to field experience is discussed. (authors)
Additional details
Additional titles
- Original title (English)
- Contribution des expertises sur materiaux a la resolution des problemes rencontres dans les reacteurs a eau pressurisee
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- Imprint Title
- Contribution of materials investigation to the resolution of problems encountered in pressurized water reactors
- Imprint Pagination
- (v.1-2) 1175 p.
- Journal Page Range
- p. 107-116
Conference
- Title
- Fontevraud 5 International symposium
- Dates
- 23-27 Sep 2002
- Place
- Fontevraud - Royal Abbey (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 35038667
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACK PROPAGATION; FRACTURE MECHANICS; INCONEL 600; MATERIALS TESTING; PWR TYPE REACTORS; STRESS CORROSION; WELDED JOINTS
- Descriptors DEC
- ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; JOINTS; MATERIALS; MECHANICS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs. Imprint:Contribution des expertises sur materiaux a la resolution des problemes rencontres dans les reacteurs a eau pressurisee