采用U 型弯曲试样浸泡试验，对比研究了核电厂常温水池用304L与S32101不锈钢焊接接头及其基体在四种溶液中的应力腐蚀开裂（SCC）行为。结果表明：在沸腾MgCl₂溶液中，四种试样的SCC敏感性最高，304L焊接接头发生沿晶+穿晶的混合型SCC，其余试样发生穿晶SCC，并且304L不锈钢基体的SCC敏感性高于S32101不锈钢基体的；在H₂SO₄溶液中，304L不锈钢基体与304L焊接接头发生穿晶SCC，且其SCC敏感性均随温度的升高而升高，S32101不锈钢基体与S32101焊接接头没有发生SCC；在酸性NaCl溶液中，四种试样均没有发生SCC；在模拟服役溶液中，S32101焊接接头发生穿晶SCC，并且其SCC敏感性随温度的升高而升高，其余试样没有发生SCC；在四种溶液中，两种不锈钢焊接接头的SCC敏感性均高于其基体的，且焊接接头热影响区的SCC敏感性最高。

U-shaped bending sample immersion test was used to compare and study the stress corrosion cracking (SCC) behaviors of 304L and S32101 stainless steel welded joints used in normal temperature water pool of nuclear power plant and their substrate in four solutions. The results showed that in boiling MgCl₂ solution, SCC sensitivity of four samples was the highest. 304L welded joint had a mixed intergranular + transgranular SCC, and the SCC sensitivity of 304L stainless steel substrate was higher than that of S32101 stainless steel substrate. In H₂SO₄ solution, 304L stainless steel substrate and 304L welded joint suffered transgranular SCC, and its SCC sensitivities increased with increase of temperature, S32101 stainless steel substrate and S32101 welded joints did not suffer SCC. In simulated service solution, only S32101 welded joint suffered transgranular SCC, and the SCC sensitivity of S32101 stainless sreel welded joint increased with the increase of temperature. In four solutions, the SCC sensitivity of two stainless steel welded joints was higher than that of substrates, and SCC sensitivity of heat-affected zone in welded joint was the highest.