Published 1996 | Version v1
Miscellaneous

Comparisons of simplified method JS and finite element for cracked pipes under thermal and mechanical loading

  • 1. CEA/DMT/SEMT/RDMS, CEN de Saclay, 91 - Gif-sur-Yvette (France)
  • 2. CEA/DER/SERA/LDCS, CEN de Cadarache, 13 - St. Paul-lez-Durance (France)

Description

In order to estimate the value of the parameter J for cracks in pipes, a complete set of finite element computations was conducted in France by CEA. The axisymetrical crack is located in the inner wall of the pipe. The crack depth is one quarter or one eighth of the thickness. The pipe, in austenitic steel or in ferritic steel, is subjected to internal pressure, axial load and linear thermal gradient through the thickness. The finite element results of J were compared to those predicted by simplified method Js, introduced in the A 16 guide developed by CEA for fast breeder reactor. (orig.)

Part of:
Safety and reliability of plant technology with special emphasis on components of nuclear and conventional power plants - basis for evaluation and operating experience. Vol. 1. Papers 1-30

Additional details

Additional titles

Original title (English)
Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt Komponenten nuklearer und konventioneller Kraftwerke - Beurteilungsgrundlagen und Betriebserfahrungen. Bd. 1. Vortraege 1-30.

Publishing Information

Imprint Title
Safety and reliability of plant technology with special emphasis on components of nuclear and conventional power plants - basis for evaluation and operating experience. Vol. 1. Papers 1-30
Imprint Pagination
574 p.
Journal Page Range
p. 26.1-26.10.

Conference

Title
Safety and reliability of plant technology components of nuclear and conventional power plants - basis for evaluation and operating experience.
Original Conference Title
22. MPA-Seminar: Sicherheit und Verfuegbarkeit in der Anlagentechnik -Komponenten nuklearer und konventioneller Kraftwerke - Beuteilungsgrundlagen und Betriebserfahrungen
Acronym
22. MPA seminar
Dates
10-11 Oct 1996.
Place
Stuttgart (Germany).

Optional Information

Notes
Imprint:Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt Komponenten nuklearer und konventioneller Kraftwerke - Beurteilungsgrundlagen und Betriebserfahrungen. Bd. 1. Vortraege 1-30.