【摘要】 用慢应变速率试验(SSRT)和恒载荷试验(CLT)以及低周循环载荷试验方法研究以秦山和大亚湾核电站安全为目的的有关压力边界管道破裂始发事件应力腐蚀破裂(SCC)的行为,为评价管道的结构完整性提供支持性实验数据。研究的材料有核等级(NG)主管道焊接热影响区(WHAZ)316不锈钢(SS),核等级蒸汽发生器(SG)传热管材Incolov-800、Inconel-600、Inconel-690和321SS。研究的影响因素包括材料冶金、表面喷丸处理、载荷、应变速率、循环载荷以及水化学条件对SCC的影响规律。更多还原

【Abstract】 The behavior of stress corrosion cracking (SCO was studied by slow strain rate test (SSRT), constant load test (CLT) and low frequency cyclic loading test (LFCLT). The purpose of these tests is to get the test data for evaluating the integrity of pressurized boundary of pipes in Qinshan and Guangdong nuclear power plants (NPPs). Tested materials are 316 nuclear grade stainless steel (SS) for primary pipes in welded heat affected zone (WHAZ) and tubes of heat transfer, such as Incoloy - 800, Inconel - 600, Inconel - 690 and 321 SS which are used for steam generator in PWR NPPs. The effects of material metallurgy, shotpeening treatment, tensile load, strain rate, cyclic load and water chemistry on the behavior of SCC were considered.更多还原