Published 1987 | Version v1
Book

Fatigue crack growth on a straight pipe element under sodium thermal shocks

  • 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Dept. des Reacteurs a Neutrons Rapides

Description

In FBRs several opposing factors affect the geometric evolution of the crack. Some are unfavorable (thermal shocks which induce bending and peak stresses; circumferential weld seams which also result in residual bending stresses; creep effects in high temperature loops) while others are favorable (thin gauge pipe walls; high fracture toughness of the 316 L Steel used). The authors first describe the FORTUNA test device used to apply cyclic thermal shocks on a straight pipe section submitted to a combination of primary membrane and bending stresses. The pipe element includes two circumferential cracks, one of which is located in a circumferential weld seam. Finite-element calculations of crack growth are then discussed, using linear elastic fracture mechanics and defect linespring type shell elements to allow low cost crack geometry updating. The analysis shows that thermal shocks resulting in equi-biaxial bending across the pipe wall should be one of the most severe loading configurations for leak-before-break demonstration. The experimental results will provide a basis for comparison. (orig./HP)

Additional details

Publishing Information

Publisher
Balkema.
Imprint Place
Rotterdam (Netherlands)
ISBN
90-6191-768-9
Imprint Title
Transactions of the 9th international conference on structural mechanics in reactor technology. Vol. G
Imprint Pagination
575 p.
Journal Page Range
p. 519-525.

Conference

Title
9. biennial international conference on structural mechanics in reactor technology (SMIRT-9).
Dates
17-21 Aug 1987.
Place
Lausanne (Switzerland).