PWR effect on crack initiation under equi-biaxial loading development of the experiment

Author:

Gourdin Cédric,Perez Gregory,Dhahri Hager,Courtin Stéphan,Le Roux Jean Christophe,Maitournam Habibou

Abstract

The lifetime extension of the nuclear power stations is considered as an energy challenge worldwide. That is why, the risk analysis and the study of various effects of different factors that could potentially represent a hazard to a safe long term operation are necessary. The methodology for fatigue dimensions of the Pressurized Water Reactor components (PWR) is based on the use of design curves established from test carried out in air at 20 °C on smooth specimens by integrating safety coefficient that covers the dispersion of tests associated with the effects of structures. To formally integrate these effects, some international codes have already proposed and suggested a modification of the austenitic stainless steels fatigue curve combined with a calculation of an environmental penalty factor, namely Fen, which has to be multiplied by the usual fatigue usage factor. The aim of this paper is to present a new device “FABIME2E” developed in the CEA-LISN in collaboration with EDF and AREVA. These new tests allow quantifying accurately the effect of PWR environment on semi-structure specimen. This new device combines the structural effect like equi-biaxiality and mean strain and the environmental penalty effect with the use of PWR environment during the fatigue tests.

Publisher

EDP Sciences

Subject

Industrial and Manufacturing Engineering,Mechanical Engineering,General Materials Science

Reference17 articles.

1. NUREG/CR-6909, Rev. 0, Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, 2007, O.K. Chopra and W.J. Shack

2. RCC-M − Design and Construction Rules for mechanical components of nuclear PWR islands − 2007 edition with addenda in 2008, 2009 and 2010

3. EN-13445-3 V1 standard, Unfired pressure vessels − Part 3: Design, December 2014

4. RCC-MRx, Règles de Conception et de Construction des Matériels Mécaniques des Installations Nucléaires applicables aux structures à haute température et à l'enceinte à vide ITER, AFCEN Code, Association Française pour les Règles de Conception et de Construction des chaudières Électronucléaires. www.afcen.com, 2012

5. Crack initiation under thermal fatigue: An overview of CEA experience. Part I: Thermal fatigue appears to be more damaging than uniaxial isothermal fatigue

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