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Experimental evaluation of the local failure criterion and its implementation in a damage mechanics model
International Journal of Pressure Vessels and Piping ( IF 3.0 ) Pub Date : 2021-07-24 , DOI: 10.1016/j.ijpvp.2021.104488
Hitoshi Nakamura 1 , Kensaku Arai 1 , Masaaki Kikuchi 1
Affiliation  

Herein, a tensile test for notched round–bar specimens of two types of carbon steel used in nuclear containment vessels was performed. The test results were analyzed using the Bridgman solution and an elastoplastic finite element method. The analyses showed that ductile failures in the tensile state were initiated when the sum of equivalent and mean stresses reached a critical value of the material. A simple analysis of local failure for a nuclear containment was conducted using the failure criterion, and its engineering effectiveness was then discussed. The criterion is consistent with Argon's void nucleation model and can be implemented into the void nucleation term of stress control in the Gurson–Tvergaard (GT) model. The simulation performed using the GT model, which applied the limit value of the sum of equivalent and mean stress obtained from the tensile tests to the void nucleation term, successfully reproduced failure behaviors in the specimens.



中文翻译:

局部失效准则的实验评估及其在损伤力学模型中的实现

在此,对用于核安全壳的两种碳钢的缺口圆棒试样进行了拉伸试验。使用 Bridgman 解决方案和弹塑性有限元方法对测试结果进行了分析。分析表明,当等效应力和平均应力的总和达到材料的临界值时,拉伸状态下的延性破坏就开始了。使用失效准则对核安全壳的局部失效进行了简单分析,然后讨论了其工程有效性。该准则与 Argon 的空心成核模型一致,可以实现到 Gurson-Tvergaard (GT) 模型中应力控制的空心成核项中。使用 GT 模型进行的模拟,

更新日期:2021-08-10
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