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核电厂蒸汽发生器传热管与管堵头的一次侧应力腐蚀及其防护
引用本文:丁训慎. 核电厂蒸汽发生器传热管与管堵头的一次侧应力腐蚀及其防护[J]. 核安全, 2008, 0(2): 30-34
作者姓名:丁训慎
作者单位:核动力运行研究所,武汉430074
摘    要:一次侧应力腐蚀(PWSCC)是一种晶间腐蚀,是因敏感的管子微观结构、高的残余拉应力和工作应力以及腐蚀性环境(高温水)引起的。防止PWSCC的措施包括:选择适当的管子材料、减小残余拉应力和改善腐蚀性环境、激光焊接衬管以及镀镍修补。

关 键 词:核电厂  蒸汽发生器  一次侧应力腐蚀(PWSCC)  防护

PWSCC and its Protection of Steam Generator Tubes and Tube Plugs in Nuclear Power Plants
DING Xunshen. PWSCC and its Protection of Steam Generator Tubes and Tube Plugs in Nuclear Power Plants[J]. Nuclear Safety, 2008, 0(2): 30-34
Authors:DING Xunshen
Affiliation:DING Xunshen ( Research Institute of Nuclear Power Operation, Wuhan 430074, China)
Abstract:Primarg water stress corrosion cracking (PWSCC) is an intergranular stress corrosion cracking. PWSCC is believed to be caused by susceptible tubing microstructure, high applied and residual tensile stress, a corrosive environment ( high temperature water). Following measures are used to prevent the PWSCC : selection of suitable tube material, decreasing residual tensile stress and improving corrosive environment, lasex-welded sleeve and nickelage repair.
Keywords:nuclear power plant  steam generator  PWSCC  protection
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