Published 1977 | Version v1
Book

Crack growth rate analysis in PWR reactor piping

  • 1. Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France)
  • 2. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. des Etudes Mecaniques et Thermiques

Description

The survey of crack growth on PWR reactor primary circuit pipings is the subject matter of the Aquitaine-1 Program. - This program includes an experimental part on piping elements made of stainless steel AISI 316, L scale 1/4 of primary pipings. These pipings are subject to cyclic variations of cold pressure, then to 2900C in water, utilizing a specific test loop. At 2900C the pressure variations are between the atmosphere and 160 bars at 4 cycles/hr. With the above conditions the experimental part constitutes a realistic approach to phenomena pertaining to defects propagation in actual operating conditions. A first phase consisted of characterizing the material. The speed of cracking was determined on test-piece CT in the various environment conditions: air 200C, air 3200C, water 3200C. Furthermore, an evaluation of the influence of the cycling frequency on that speed had been made. (Auth.)

Additional details

Publishing Information

Publisher
North-Holland.
Imprint Place
Amsterdam, Netherlands
ISBN
0 444 85062 7
Imprint Title
Structural mechanics inreactor technology
Journal Page Range
v. F p. F 7/6 1-15.

Conference

Title
4. international conference on structural mechanics in reactor technology.
Dates
15 - 19 Aug 1977.
Place
San Francisco, USA.