Tubesheet and expansion transition cracking at Doel 3 and Tihange 2
Description
The field experience from Doel 2, Doel 3, and Tihange-2 shows that mill-annealed Alloy 600 tubes may be very susceptible to primary water stress corrosion cracking in the tubesheet area, both in the roll transition and the expanded area for the full thickness of the tubesheet. Cracks initiate at areas of high residual stress resulting from mechanical or hydraulic expansion. These areas include the roll transition (with or without a kiss roll), areas of major rolling anomalies, and also areas of minor discontinuities, even those which are considered acceptable (and are practically unavoidable) by normal manufacturing practices. A large number of cracked tubes may not be noticed by the normal inspection methods and may lead to only very small service leaks. Thus, many units with mill-annealed Alloy 600 tubing might be affected by an undetected stress corrosion problem. The long-term operational and safety significance of the degradation progress is an unclear issue. An extensive R and D program has been launched to identify appropriate preventive and corrective actions for the 4 recent Belgian units (Doel 3 and 4, and Tihange 2 and 3). A full-length rotopeening has already been performed in the tubesheet areas of the units Doel 4 and Tihange 3
Additional details
Publishing Information
- Imprint Title
- Proceedings: 1985 workshop on primary-side stress corrosion cracking of PWR steam generator tubing
- Journal Page Range
- p. 1.1-1.35.
- Report number
- EPRI-NP--5158
Conference
- Title
- Workshop on primary-side stress corrosion cracking of PWR steam generator tubing.
- Dates
- 20-22 Mar 1985.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19046287
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- ALLOY-NI76CR15FE8; CRACK PROPAGATION; CRACKS; DOEL-2 REACTOR; DOEL-3 REACTOR; EDDY CURRENT TESTING; EXPERIMENTAL DATA; IN-SERVICE INSPECTION; LEAKS; MECHANICAL PROPERTIES; REACTOR SAFETY; SHEETS; STRESS CORROSION; TIHANGE-2 REACTOR; TUBES
- Descriptors DEC
- ALLOYS; ALUMINIUM ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; DATA; ELECTROMAGNETIC TESTING; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; INFORMATION; INSPECTION; IRON ALLOYS; MATERIALS TESTING; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NONDESTRUCTIVE TESTING; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; TESTING; THERMAL REACTORS; TITANIUM ADDITIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS