RESIDUAL STRESS IN CLADDING - ANALYTICAL AND EXPERIMENTAL VALUES ON A 1 TO 5 SCALE PV MODEL
The paper presents an analysis of importance of cladding residual stresses (CRS) for the realistic (best estimate) lifetime prediction for nuclear reactor pressure vessels. The analysis has been based on a survey of the previous investigations, on specially performed measurements (on specimen, on 1/5 scale PWR nozzle and on 1/5 scale PWR vessel), and on analytical models for stress analysis, fracture mechanics and lifetime prediction. The measurments have been made using the centre hole, air abrasive method. This stress analysis model has been based on a fictive temperature field (for the CRS simulation) and on ADINA and BERSAFE finite element codes. The fracture mechanics analysis has been performed according to the virtual crack extension method (J-integral), while the COVASTOL computer code has been used for the probabilistic lifetime prediction. A high (over 250 MPa) has been determined, and its importance for the vessel integrity quantitatively estimated.
Bibliographic Reference: 8TH INTERNATIONAL CONFERENCE ON STRUCTURAL MECHANICS IN REACTOR TECHNOLOGY, BRUXELLES (BELGIUM), AUG. 19-23, 1985 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 32097 ORA
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Record Number: 1989123070600 / Last updated on: 1987-01-01
Available languages: en