RESIDUAL STRAIN IN A FUSION-REACTOR 1ST-WALL COMPONENT SUBJECTED TO THERMAL FATIGUE

被引:6
作者
ALBERTINI, G
ANDRE, G
MATERA, R
MIELE, P
MEROLA, M
PERRIN, M
RUSTICHELLI, F
机构
[1] LAB L BRILLOUIN SPECTROMETRIE NEUTR,SACLAY,FRANCE
[2] CTR COMMUN RECH ISPRA,IST MAT AVANZATI,I-21020 ISPRA,ITALY
[3] POLITECN MILAN,CTR STUDI NUCL ENRICO FERMI,I-20133 MILAN,ITALY
[4] UNIV ANCONA,IST FIS MED,I-60131 ANCONA,ITALY
来源
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING | 1991年 / 148卷 / 02期
关键词
D O I
10.1016/0921-5093(91)90823-6
中图分类号
TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
The residual strain in a mock-up of a first wall for nuclear fusion reactors is investigated. An AISI 316L steel component was subjected to 27 000 thermal cycles simulating the heat flux variations during reactor operations, in an experimental station built for this purpose at the JCR Ispra. The residual strain map was obtained theoretically by using finite element analysis. The numerical results are compared with the strain values measured along two lines, using neutron diffraction. Although the theoretical computation does not consider the actual state of the component, including the effects of undesirable thermal variations connected to preparation and handling, good agreement was obtained between theoretical prediction and measured values, indicating that neutron diffraction is a refined tool for studying residual strains.
引用
收藏
页码:211 / 217
页数:7
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