Application of the Small-Punch Test to Irradiated Reactor Vessel Steels in the Brittle-Ductile Transition Region
Application of the Small-Punch Test to Irradiated Reactor Vessel Steels in the Brittle-Ductile Transition Region
复制标题
小冲头试验在辐照反应堆容器钢脆韧转变区的应用
DOI：
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发表时间：
2008
期刊：
影响因子：
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通讯作者：
H. Viehrig
中科院分区：
文献类型：
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作者：
T. Linse;M. Kuna;J. Schuhknecht;H. Viehrig
本文提出了一种利用小冲杆试验确定脆-韧过渡区硬化参数和脆性区威布尔参数的方法。研制了一种小冲杆试验装置，在热室中测量了反应堆容器钢辐照前后不同温度下的载荷-位移曲线。在用于识别硬化特性的全局优化算法中，通过使用借助于先前由FEM生成的数据库训练的神经网络来避免耗时的有限元法（FEM）计算。将识别的材料特性与拉伸试验的数据进行比较（如果可用）。分析了辐照和温度对材料和断裂行为的影响。
In this paper, a method is applied for the identification of hardening parameters in the brittle-ductile transition region and the determination of Weibull parameters in the brittle region using small-punch tests. A small-punch-test device is developed to measure the load-displacement curve for non-irradiated and irradiated specimens of a reactor vessel steel at different temperatures inside a hot cell. In a global optimization algorithm for the identification of hardening properties, time-consuming finite element method (FEM) calculations are avoided by using neural networks that were trained with the help of a database previously generated by FEM. Identified material properties are compared with data from tensile tests, where available. The influence of irradiation and temperature on the material and fracture behavior is analyzed.