Statistical analysis and model prediction for steam generator degradation
Creators
- 1. Tecnatom, Madrid (Spain)
- 2. ODEC, Madrid (Spain)
Description
Steam Generator tubes are susceptible to different types of mechanical and corrosion-induced damage. Among the causes underlying tube deterioration, special mention may be made of the phenomenon known as stress corrosion cracking, which is classified as PWSCC when occurring on the primary side and ODSCC when appearing on the secondary. In view of the progressive deterioration of the steam generator tubes experienced in certain Spanish plants, it is advisable that a tool be developed allowing the evolution of different types of degradation, and consequent tube plugging, to be estimated, in order to clarify the maintenance tasks to be performed during each plant outage, gain insight into the remaining lifetime of these components and, finally, incorporate the information obtained into a steam generator replacement strategy. For this reason, a study of the two aforementioned types of defects has been performed at the ALMARAZ 1 and 2 and ASCO 1 and 2 plants. This study consisted of creating an advanced prediction model capable of estimating both the number of affected tubes identified in subsequent refueling outages and the magnitude of the possible indications found, be they previously existing indications undergoing evolution or newly developed indications. In this way, and following establishment of plugging limits, it is possible to determine the number of tubes to be plugged or repaired. Long-term predictions make it possible to draw up a strategy for subsequent refueling outages, up to steam generator replacement
Additional details
Publishing Information
- Publisher
- ASM International.
- Imprint Place
- Materials Park, OH (United States)
- ISBN
- 0-87170-506-0
- Imprint Title
- 12th International Conference on NDE in the Nuclear and Pressure Vessel Industries
- Imprint Pagination
- 521 p.
- Journal Page Range
- p. 253-257.
Conference
- Title
- 12. international conference on non-destructive evaluation in the nuclear and pressure vessel industries.
- Dates
- 10-13 Oct 1993.
- Place
- Philadelphia, PA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26070074
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALMARAZ-1 REACTOR; ALMARAZ-2 REACTOR; ASCO-1 REACTOR; ASCO-2 REACTOR; CRACK PROPAGATION; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR FUELING; REACTOR MAINTENANCE; REACTOR SHUTDOWN; STEAM GENERATORS
- Descriptors DEC
- BOILERS; ENRICHED URANIUM REACTORS; MAINTENANCE; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SHUTDOWN; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-931061--.