Parameters influencing the transgranular stress corrosion cracking behaviour of austenitic stainless steels in systems conveying reactor coolant
- 1. Framatome ANP (Germany)
- 2. E.ON Kernkraft (Germany)
- 3. RWE Power (Germany)
- 4. HEW - (Germany)
- 5. EnBW - (Germany)
Description
During replacement of an auxiliary system in the German PWR KKS (NPP Stade) a damage was detected in a valve housing and in the connected piping both made from stabilised austenitic stainless steel. During operation stagnant conditions are present in this area. Based on the failure analysis chloride induced stress corrosion cracking (SCC) was found as the dominating root cause. In the open literature many cases of corrosion observed in the water/steam interface in valve components as well as in adjacent portions of auxiliary circuits made of un-stabilized stainless steels are mentioned. A common feature of the reported cases is that transgranular cracking was found. Extensive laboratory investigations revealed that non-stabilised austenitic stainless steels are also sensitive to transgranular cracking in boric acid solutions particularly in concentrated solutions. Often these solutions are contaminated with chlorides and/or oxygen is present. Taking into account the literature data the question could arise whether the above mentioned cracking may be also caused by boric acid attack. Thus, for stabilised stainless steels laboratory exposure tests at 80 C in saturated aerated boric acid solution and at 300 C in (at 100 C) saturated, oxygen free boric acid solution have been performed. Double-U-bend specimens and wedge loaded 1T-CT specimens made of Ti- and Nb-stabilised austenitic stainless steels were used. The results revealed no evidence of crack initiation and crack growth. Based on the laboratory results and the literature data an attempt is undertaken to separate parameters influencing chloride induced SCC from the effect of boric acid. (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. 137-147
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
- 35038670
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORIC ACID; CHLORIDES; CRACK PROPAGATION; MATERIALS TESTING; PWR TYPE REACTORS; STAINLESS STEEL-304; STAINLESS STEEL-316; STRESS CORROSION
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; BORON COMPOUNDS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHLORINE COMPOUNDS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HALIDES; HALOGEN COMPOUNDS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; OXYGEN COMPOUNDS; POWER REACTORS; REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEEL-CR19NI10; STEELS; TESTING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 15 refs. Imprint:Contribution des expertises sur materiaux a la resolution des problemes rencontres dans les reacteurs a eau pressurisee