Stress corrosion cracking on cold-worked austenitic stainless steels in PWR environment
Creators
- 1. Univ. de Bordeaux I, LMP, Cours de la liberation, Talence (France)
- 2. EDF R and D, MMC, Site des Renardieres, Moret sur Loing cedex (France)
- 3. EDF DIN, CEIDRE, Saint-Denis (France)
- 4. EDF DIS, SEPTEN, Villeurbanne (France)
Description
Over the few years, limited cases of IGSCC have been detected in cold-worked areas of non-sensitized austenitic stainless steel components of French PWRs. Our first study of this phenomenon determined the required conditions for SCC of 304L in the laboratory after brief exposures to the PWR primary water environment : cold-work to a hardness > 240 HV0,1 for true initiation and > 310 HV0,1 for propagation, and dynamic loading. A SCC propagation model is developed here by investigating the effect of periodic and partial unloading/reloading, material properties (304L vs 316L) and cold-work (rolling (RCW) vs tensile (TCW) cold-work). It is shown that RCW materials undergo TGSCC or IGSCC and TCW materials IGSCC. The loading ratio R modifies the mechanism of the cracking and seems to decrease the stress intensity factor threshold (KISCC). No obvious effect of the hold time is observed on the crack growth rate but the initiation time depends on the hold time. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-89-5
- Imprint Title
- 13th International conference on environmental degradation of materials in nuclear power systems
- Imprint Pagination
- 388 Megabytes
- Journal Page Range
- [16 p.]
Conference
- Title
- 13. International conference on environmental degradation of materials in nuclear power systems
- Dates
- 19-23 Aug 2007
- Place
- Whistler, BC (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 39116926
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AUSTENITIC STEELS; COLD WORKING; CRACK PROPAGATION; CRACKING; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; ROLLING; STAINLESS STEEL-304L; STAINLESS STEEL-316L; STRESS CORROSION; TENSILE PROPERTIES
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; DECOMPOSITION; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FABRICATION; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; MATERIALS WORKING; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; POWER REACTORS; PYROLYSIS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3-L; STEEL-CR19NI10-L; STEELS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 refs., 3 tabs., 21 figs.