Research on temper bead welding procedure test of the low alloy steel for reactor pressure vessel

JIN Liang; KUANG Yanjun; HUANG Tengfei; SUN Guang; QIU Zhensheng; CHEN Liang

doi:10.7512/j.issn.1001-2303.2020.06.06

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Research on temper bead welding procedure test of the low alloy steel for reactor pressure vessel
Vol. 50, Issue 6, Pages: 39-43(2020)
Published：2020
DOI： 10.7512/j.issn.1001-2303.2020.06.06
稿件说明：

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DOI：

JIN Liang, KUANG Yanjun, HUANG Tengfei, et al. Research on temper bead welding procedure test of the low alloy steel for reactor pressure vessel[J]. Eletric Welding Machine2020, 50(6): 39-43. DOI： 10.7512/j.issn.1001-2303.2020.06.06.

摘要

为解决核电厂关键设备在役期间焊接返修后无法实施传统焊后热处理的难题

采用机械-钨极惰性气体保护焊分别在室温和150℃预热条件下对反应堆压力容器用低合金钢进行回火焊道焊接工艺试验

然后测试焊接热影响区的显微硬度、显微组织及冲击韧性。试验结果表明:通过合理控制前三层的焊接热输入

可有效降低焊接热影响区的硬度

并获得综合性能较好的回火索氏体组织

室温条件下的回火焊道焊接热影响区在0℃和-20℃的冲击吸收能量均高于设计要求值。

Abstract

The conventional postweld heat treatment（PWHT） can not be applied to the key equipment of nuclear power plant after repair welding during service. In order to solve this problem

a mechanized gas tungsten arc welding（GTAW） is used for temper bead welding procedure test of the low alloy steel for reactor pressure vessel under the preheating conditions at room temperature and 150 ℃ respectively

and then the microhardness

microstructure and impact toughness of the heat affected zone（ HAZ） are tested. The results show that the microhardness can be effectively reduced by properly controlling the heat input ratios of the first three layers

and the tempered sorbite structure with good comprehensive properties can be obtained in the HAZ. Both the impact absorption energies at 0 ℃ and 20 ℃ of the HAZ of the temper bead under the preheating conditions at room temperature are higher than the design requirements.