Evaluation of critical fracture stress in low alloy steels by finite element analysis of small punch test

被引:0
作者
Kim, Min-Chul [1 ]
Lee, Jae Bong [2 ]
Oh, Yong Jun [3 ]
Lee, Bong Sang [1 ]
机构
[1] Korea Atom Energy Res Inst, Div Nucl Mat Technol, Taejon, South Korea
[2] Chungbuk Natl Univ, Dept Safety Engn, Cheongju, South Korea
[3] Hanbat Natl Univ, Div Adv Mat Engn, Daejeon, South Korea
来源
PROGRESSES IN FRACTURE AND STRENGTH OF MATERIALS AND STRUCTURES, 1-4 | 2007年 / 353-358卷
关键词
small punch test; reactor pressure vessel; finite element analysis; critical fracture stress;
D O I
10.4028/www.scientific.net/KEM.353-358.416
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The critical fracture stresses (sigma(*)(f(SP))) various low alloy steels for a reactor pressure vessel(RPV) were evaluated by a small punch test (SP test) and a finite element analysis (FEA) in the cleavage temperature region(-150 similar to-196 degrees C). The load-displacement curves and distances from the center to the fracture surface (D-f) of the FEA results are in good agreement with the experimental results. The maximum principal stresses (SP fracture stresses, sigma(f(SP))) were determined from the FE analysis, when the maximum load was applied to the SP test. The SP critical fracture stress, sigma*(f(SP)) in various reactor pressure vessel (RPV) steels was found to have a linear relationship with the values obtained from the precracked specimens (sigma*(f(PCVN))). The sigma*(f(sp)) shows a lower value than sigma*(f(PCVN)) because the SP specimen had a lower triaxial stress condition. However, this result indicates that a small punch test could be a useful method to evaluate the cleavage fracture behavior of low alloy steels.
引用
收藏
页码:416 / +
页数:2
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