首页> 外文会议>Transactions of the 17th international conference on structural mechanics in reactor technology (SMiRT 17) >The Evaluation of Ductile-Brittle Transition Temperature Before and afterNeutron Irradiation in RPV Steels Using a Small Punch Test
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The Evaluation of Ductile-Brittle Transition Temperature Before and afterNeutron Irradiation in RPV Steels Using a Small Punch Test

机译:使用小冲孔试验评估RPV钢中中子辐照前后的脆性转变温度

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A small punch (SP) test was performed to evaluate the ductile-brittle transition temperature before and afterrnneutron irradiation in reactor pressure vessel (RPV) steels produced by different manufacturing (refining) processes.rnThe results were compared to the standard transition temperature shifts from the Charpy test and Master Curve fracturerntoughness test in accordance with the ASTM standard E1921. The samples were taken from 1/4t location of the vesselrnthickness and machined into a 10x10x0.5mm dimension. Irradiation of the samples was carried out in the researchrnreactor at KAERI (HANARO) at about 290 ℃ of the different fluence levels respectively. SP tests were performed inrnthe temperature range of RT to -196℃ using a 2.4mm diameter ball. For the materials before and after irradiation, SPrntransition temperatures (TSP), which are determined at the middle of the upper and lower SP energies, showed a linearrncorrelation with the Charpy index temperature, T41J. Tsp from the irradiated samples was increased as the fluence levelrnincreased and was well within the deviation range of the unirradiated data. The TSP had a correlation with the referencerntemperature (T0) from the master curve method using a pre-cracked Charpy V-notched (PCVN) specimen.
机译:进行了小冲孔(SP)测试,以评估通过不同制造(精炼)工艺生产的反应堆压力容器(RPV)钢中子辐照前后的韧性-脆性转变温度。根据ASTM标准E1921进行的夏比试验和主曲线断裂韧性试验样品取自容器厚度的1 / 4t处,并加工成10x10x0.5mm的尺寸。在KAERI(HANARO)的研究反应器中分别在大约290℃的不同通量水平下对样品进行辐照。在室温至-196℃的温度范围内,使用直径为2.4mm的球进行SP测试。对于辐照前后的材料,在上下SP能量的中间确定的SPrn转变温度(TSP)与夏比指数温度T41J呈线性相关。随着注量水平的增加,来自辐照样品的TSP增加,并且恰好在未辐照数据的偏差范围内。 TSP与使用预裂纹的夏比V型缺口(PCVN)试样的主曲线法得出的参考温度(T0)相关。

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