首页> 外文会议>International Conference on Processing amp; Manufacturing of Advanced Materials; 20060704-08; Vancouver(CA) >Repair Welding of Irradiated Reactor Vessel Steel by Low Heat Input GTAW and LBW
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Repair Welding of Irradiated Reactor Vessel Steel by Low Heat Input GTAW and LBW

机译:低热输入GTAW和LBW对辐照反应堆容器钢的修复焊接。

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Weldability in neutron-irradiated low alloy steel for a reactor (pressure) vessel has been studied by a temper-bead welding technique using low-heat-input GTAW and LBW(YAG). The base and weld metals of low alloy steel with clad or without clad were irradiated up to 1.4×10~(24) n/m~2 (>1 MeV) at 290 ℃, which approximately corresponds to the maximum neutron fluence of a 60-year-operation plant's vessel. The mechanical property tests, such as tensile, impact side bend and hardness, were carried out after the repair-welding. The weld cracking did not occur in base and weld metals of irradiated low alloy steels during the repair-welding by GTAW and LBW. Small porosities were formed in the first and second layers of the repair weld metal. Only a few porosities were found in weld metal compared with in base metal. From the results of mechanical properties, the weld metal of low alloy steel could be welded up to a He concentration of 12.9 appm, while the base metal could be done up to only 1.7 appm He. On the other hand, weld cracks occurred in stainless steel and Ni base alloy clad on low alloy steel caused by He bubble formation Based on these results, the rule of repair-welding procedure selection was proposed for the reactor (pressure) vessel.
机译:已经通过使用低热量输入GTAW和LBW(YAG)的回火珠焊技术研究了用于反应堆(压力)容器的中子辐照低合金钢的可焊性。在290℃时,低合金钢的包层或不包层的基础金属和焊缝金属的辐照度高达1.4×10〜(24)n / m〜2(> 1 MeV),大约相当于60的最大中子注量。年运营工厂的船只。在补焊之后进行了机械性能测试,例如拉伸,冲击侧弯曲和硬度。在GTAW和LBW的补焊过程中,辐照低合金钢的母材和焊缝金属均未发生焊缝开裂。在修补焊缝金属的第一层和第二层中形成了小孔隙。与母材相比,在焊缝金属中只有很少的孔隙。从机械性能的结果来看,低合金钢的焊接金属可以焊接到12.9 appm的He浓度,而母材只能焊接到1.7 appm的He。另一方面,由于He气泡的形成,在低合金钢上包覆的不锈钢和Ni基合金中发生了焊接裂纹。基于这些结果,提出了反应堆(压力)容器的补焊程序选择原则。

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