Published 1987
| Version v1
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Behaviour of the nozzle corner region during the first phase of the fatigue test on scaled models of pressure vessels (JRC Vessel A)
Description
The work presented here deals mainly with the stress and fracture mechanics aspects of the first phase of the structural reliability experimental program based on the scaled experimental vessel at Ispra. The overall research and experiments make also part of the structural reliability assessment extrapolation pattern for the full-scale structures. The work presented here deals with the problem of the nozzle corner cracks induced by the fatigue under the pressure cycling
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Additional details
Publishing Information
- Imprint Pagination
- 98 p.
- Report number
- EUR--11023
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- European Commission (EC), Brussels (Belgium)
- INIS RN
- 19068729
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CLADDING; CRACK PROPAGATION; CRACKS; EUROPEAN COMMUNITIES; FATIGUE; NOZZLES; PRESSURE DEPENDENCE; PRESSURE VESSELS; PWR TYPE REACTORS; RESIDUAL STRESSES
- Descriptors DEC
- CONTAINERS; DEPOSITION; ENRICHED URANIUM REACTORS; INTERNATIONAL ORGANIZATIONS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; STRESSES; SURFACE COATING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS