Experience with steam generators of the KWU-concept
- 1. Kraftwerk Union A.G., Erlangen (Germany, F.R.)
Description
Eleven plants equipped with KWU pressurized water reactors and 34 steam generators are currently in power operation. Eddy-current tests are conducted at regular intervals to check the condition of the steam generator tubes. The routine inspection techniques are complemented by analysing techniques characterized by rotating ultrasonic high-frequency probes and rotating eddy-current narrow-field-probes. The two steam generators of the Obrigheim plant equipped with Inconel 600 tubing experienced severe intergranular stress corrosion. These steam generators have to be replaced. The operating experience with Incoloy 800 tubed steam generators shows that there is only one area of concern with respect to corrosion attack: The tube wastage, a phosphate induced wall-thinning which occurs in a specific zone within the hot and cold side sludge pile above the tube sheet. From the inspection findings and metallographic examinations of removed tubes it was concluded that three remedial actions have to be implemented: (i) minimization of low-flow zones in the steam generator; (ii) prevention of condenser leakages; (iii) reduction of corrosion product transport into the steam generators. To meet these objectives, several improvements and modifications were introduced into the steam generators and the steam-water-cycle of plants under construction, i.e. high integrity condensers using Cu-free materials, filtration of the feedwater, All Volatile Treatment (AVT) with pH-values above 9.8 in the feedwater etc. First experience from a unit operating according to this philosophy is excellent. To all units operating on phosphate chemistry it was recommended to implement the above-mentioned features emphasizing the high integrity condensers. (author)
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna
- ISBN
- 92-0-050883-9
- Imprint Title
- Reliability of reactor pressure components
- Imprint Pagination
- 415 p.
- Series
- Proceedings series.
- Journal Page Range
- p. 87-103.
Conference
- Title
- International symposium on reliability of reactor pressure components.
- Dates
- 21-25 Mar 1983.
- Place
- Stuttgart (Germany, F.R.).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 15014122
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOY-FE46NI33CR21; ALLOY-NI76CR15FE8; CORROSION PRODUCTS; EDDY CURRENT TESTING; GERMAN FR ORGANIZATIONS; IN-SERVICE INSPECTION; MINIMIZATION; PWR TYPE REACTORS; SECONDARY COOLANT CIRCUITS; STEAM GENERATORS; STRESS CORROSION; TUBES; ULTRASONIC TESTING
- Descriptors DEC
- ACOUSTIC TESTING; ALLOYS; ALUMINIUM ADDITIONS; BOILERS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; ELECTROMAGNETIC TESTING; HEAT RESISTING ALLOYS; INCOLOY ALLOYS; INCONEL ALLOYS; INSPECTION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; NATIONAL ORGANIZATIONS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NONDESTRUCTIVE TESTING; OPTIMIZATION; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING; TITANIUM ADDITIONS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- IAEA-SM--269/23.