VALIDATION OF CRACK-LIKE DEFECT FATIGUE ANALYSIS

被引：0

作者：

AUTRUSSON, B

MOULIN, D

ACKER, D

机构：

[1] Département des Etudes Mécaniques et Thermiques, Centre d'Etude Nucléaire de Saclay, Commissariat à l'Energie Atomique, B.P. 2

来源：

NUCLEAR ENGINEERING AND DESIGN | 1991年 / 129卷 / 03期

关键词：

D O I：

10.1016/0029-5493(91)90139-9

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

French nuclear construction codes, RCC-M [1] for Pressurized-Water Reactors (PWRs) and RCC-MR [2] for Liquid-Metal Reactors, propose design methodologies to appraise the fatigue damage risk in the sharp notches tip or crack-like defects. This paper continues those presented by Autrusson et al. (1988) and R. Roche (1990), to follow the experimental validation of these analysis methods, aiming to predict initiation of cracks in crack-like defects existing on start-up pressure vessel components. The comparison of analysis results with experimental tests permits to propose some modifications in order to obtain a satisfactory correlation with the classical fatigue curve relevant for the material.

引用

页码：307 / 313

页数：7