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Analysis of cladding residual stresses and their influence on the structural reliability of LWR pressure vessels

Authors
Journal
International Journal of Pressure Vessels and Piping
0308-0161
Publisher
Elsevier
Publication Date
Volume
22
Issue
2
Identifiers
DOI: 10.1016/0308-0161(86)90080-3
Disciplines
  • Physics

Abstract

Abstract The work presented here investigates cladding residual stress (CRS) and its important in realistic (best-estimate) lifetime prediction for nuclear reactor pressure vessels. The analysis is based on a survey of previous investigations, on the authors' own specially performed measurements (on specimens, on a 1:5 scale PWR nozzle and on a 1:5 scale PWR vessel), and on analytical models for stress analysis, fracture mechanics and lifetime prediction. The measurements were made using the centre-hole, air-abrasive method. The stress analysis model was based on a fictitious temperature field (for the CRS simulation) and on the ADINA and BERSAFE finite element codes. The fracture mechanics analysis was performed according to the virtual crack extension method ( J- integral ), while the COVASTOL computer code was used for the probabilistic lifetime prediction. A high (250–400 MPa) CRS was determined, and its importance to the vessel integrity estimated quantitatively.

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