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HOT CELL PULSED LASER WELDING OF NEUTRON IRRADIATED TYPE 304 STAINLESS STEEL WITH A MAXIMUM DAMAGE DOSE OF 28 DPA

机译:最大损伤剂量为28 DPA的中子辐照304不锈钢的热室脉冲激光焊接

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Radiation-induced degradation of reactor pressure vessels and internals is a concern to the aging nuclear fleet and welding solutions will be required if repair of these irradiated components is deemed necessary. However, the weldability of highly irradiated austenitic materials is significantly diminished due to the presence of irradiation induced helium in the material matrix. Helium-induced weld cracking is a complex phenomenon that is related to the concentration of helium, the heat input from the welding process, and stresses generated during cooling of the weld. During conventional high heat input welding methods such as gas tungsten arc welding, helium bubbles can coalesce and grow on base metal grain boundaries within the heat-affected zone which subsequently causes intergranular cracking. The objective of this work was to obtain weldability data by characterizing welds made on highly activated, neutron irradiated Type 304 stainless steel containing both radiation-induced helium and microstructural damage such as void swelling. All irradiated materials welding was performed inside a Westinghouse hot cell utilizing a pulsed Nd.YAG laser with welds made on three rectangular samples of highly activated Type 304 stainless steel. The rectangular samples were cut and milled in-cell from sections previously obtained from two neutron reflector hex blocks. The hex blocks are U.S. Department of Energy owned material and were irradiated for approximately 13 years in the EBR-II sodium cooled fast reactor from 1982 until 1995. The three samples selected for welding have nominal damage doses of approximately 0.4. 11, and 28 dpa with corresponding estimated helium contents of 0.2, 3 and 8 appm helium, respectively. A number of different weld parameter sets were utilized and included variations of travel speed, wire feed speed and tens-to-work distances. The parameter sets allowed for a range of effective weld heat input levels to be compared. Single pass and multiple pass as well as wire fed and autogenous welds were made. This paper presents the results from post-weld evaluations performed on the three welded irradiated samples, focusing on the reduced tendency for cracks to form adjacent to the weld as a function of weld parameters, lens-to-work distance and helium content.
机译:辐射诱发的反应堆压力容器和内部零件的退化是核反应堆老化的一个问题,如果认为需要维修这些被辐射的部件,则需要焊接解决方案。但是,由于材料基体中存在辐照引起的氦气,高辐照度奥氏体材料的可焊性显着降低。氦气引起的焊缝开裂是一种复杂的现象,与氦气的浓度,焊接过程中输入的热量以及焊缝冷却过程中产生的应力有关。在诸如气体钨极电弧焊的常规高热输入焊接方法中,氦气气泡会聚结并在热影响区域内的贱金属晶粒边界上生长,随后会引起晶间裂纹。这项工作的目的是通过表征在高活化,中子辐照的304型不锈钢上进行的焊缝的特征来获得可焊性数据,该材料既包含辐射诱发的氦气,又包含微观结构损伤(如溶胀)。所有辐照材料的焊接均在Westinghouse热室中进行,采用脉冲Nd.YAG激光,并在三个高度活化的304型不锈钢矩形样品上进行焊接。从先前从两个中子反射器六角形块获得的切片中切割矩形样品,并在晶胞中进行研磨。六角形块是美国能源部拥有的材料,从1982年到1995年在EBR-II钠冷快堆中辐照了约13年。选择用于焊接的三个样品的名义损伤剂量约为0.4。 11 dpa和28 dpa,相应的估计氦含量分别为0.2、3和8 appm氦。利用了许多不同的焊接参数集,包括行进速度,送丝速度和十到工作距离的变化。参数集允许比较一系列有效的焊接热量输入水平。进行了单道次和多道次以及送丝和自生焊缝。本文介绍了对三个焊接的辐照样品进行的焊后评估结果,重点是根据焊接参数,透镜到工作距离和氦含量的变化,减少了在焊缝附近形成裂纹的趋势。

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