Published 1986
| Version v1
Journal article
Flaw analysis in steam generator tubes
Creators
- 1. Electricite de France, 75 - Paris. Service de la Production Thermique
- 2. Framatome, Paris La Defense (France)
Description
The flaw assessment programme undertaken in France for PWR steam generator tubes affected by stress corrosion cracking is presented. Failure criteria was deduced from burst tests on various crack configurations. Stresses and critical crack sizes were estimated for all operating conditions. The corresponding leak rates during normal operation were computed after validation of the model. Then it was shown that a significant primary-to-secondary leak should precede tube failure. (author)
Additional details
Publishing Information
- Journal Title
- Int. J. Press. Vessels Piping
- Journal Volume
- 25
- Journal Issue
- 1-4
- Series
- Int. J. Press. Vessels Piping.
- Journal Page Range
- 267-278
- ISSN
- 0308-0161
- CODEN
- PRVPA
Conference
- Title
- 4. International Seminar on Assuring Structural Integrity of Steel Reactor Pressure Boundary Components.
- Dates
- 26-27 Aug 1985.
- Place
- Ispra (Italy).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 18065906
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; DEFECTS; FAILURES; LEAKS; PIPES; PWR TYPE REACTORS; SAFETY ANALYSIS; STEAM GENERATORS; STRESS CORROSION; TUBES
- Descriptors DEC
- BOILERS; CHEMICAL REACTIONS; CORROSION; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS