Belgian approach to steam generator tube plugging for primary water stress corrosion cracking
- TRACTEBEL, Brussels (Belgium)
- Laboratoire Belge de l'Industrie Electrique (LABORELEC), Linkebeek (Belgium)
For a number of years, three Belgian nuclear power plants have experienced primary water stress corrosion cracking (PWSCC) in the expansion transition area on a very large number of tubes. One of the plants has part depth rolled tubes and the others have full depth expansion. The report presents a review of the leakage experience associated with (PWSCC) in the Doel 2, Doel 3 and Tihange 2 Nuclear Power Plants and illustrates the type of cracking observed on pulled tubes from Doel 2 and Doel 3. The Belgian units operate with numerous through wall cracks without impairing the safety and the reliability of the plants. This is achieved by a safety approach based on the extensive use of advanced non-destructive examination (NDE) techniques and the development of new plugging limits. These limits are derived from a realistic interpretation of NRC Regulatory Guide 1.121 and are backed up by a substantial experimental program. The report summarizes the establishment of plugging limits for both axial and circumferential cracks in the roll transition area of full depth rolled tubes. The LABORELEC eddy current rotating probe (RPC) technology and associated crack sizing methodology are also described. 8 refs., 2 figs., 1 tab.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (USA); Belgatom S.A., Brussels (Belgium)
- Sponsoring Organization:
- EPRI
- OSTI ID:
- 6959185
- Report Number(s):
- EPRI-NP-6626-M
- Country of Publication:
- United States
- Language:
- English
Similar Records
Prediction of residual stress field in mechanically expanded 0.750 inch diameter steam generator tube plugs. Part 1: 2-D solution
Alternate tube plugging criteria for steam generator tubes
Related Subjects
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
ALLOYS
BELGIUM
BOILERS
CHEMICAL REACTIONS
CORROSION
CRACKS
DOEL-2 REACTOR
DOEL-3 REACTOR
EDDY CURRENT TESTING
ELECTROMAGNETIC TESTING
ENRICHED URANIUM REACTORS
EUROPE
FLOW BLOCKAGE
INCONEL ALLOYS
LEAKS
MATERIALS TESTING
NICKEL ALLOYS
NICKEL BASE ALLOYS
NONDESTRUCTIVE TESTING
POWER REACTORS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
RELIABILITY
SAFETY
STEAM GENERATORS
STRESS CORROSION
TESTING
THERMAL REACTORS
TIHANGE-2 REACTOR
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE