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某型核电汽轮机凝汽器半侧运行分析 被引量:8

Analysis of the half-side operation of a nuclear power steam turbine condenser
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摘要 某核电汽轮机凝汽器半侧运行时发生钛管断裂,失效分析判断为流体弹性激振导致的疲劳断裂。从流体激励与管束振动响应出发,研究凝汽器半侧运行时稳态、瞬态激励对钛管振动的影响,发现凝汽器半侧运行如所带负荷偏高叠加危急疏水时容易诱发流体弹性激振。根据该型凝汽器的管束设计特点,对激振敏感区域的钛管进行堵管和加防磨条处理,同时优化了半侧运行时允许的最高汽轮机负荷。此外,凝汽器半侧运行时可能导致汽轮机低压转子与端部汽封的动静摩擦,该问题可以通过磨合处理解决。 Titanium tube fracture occurs during the half-side operation of a nuclear steam turbine condenser,the failure analysis is judged as the fatigue fracture caused by the fluid elastic excitation.Furthermore,from the aspects of fluid excitation and vibration response of the tube bundle,the effects of steady state and transient excitation on the vibration of the titanium tube are studied during the half-side operation of condenser.It is concluded that fluid elastic excitation is easily induced by higher load and emergency drain during the half-side operation of condenser.According to the characteristics of the tube bundle design of the condenser,the titanium tube in the sensitive region of excitation is treated with pipe plugging and adding anti-abrasive strips.And the maximum steam turbine load allowed for half-side operation is optimized.In addition,the half-side operation of the condenser may cause the static and dynamic friction between the turbine low-pressure rotor and the end of the steam seal,which can be solved by running-in.
作者 陈自强 杨璋 CHEN Ziqiang;YANG Zhang(Ningde Nuclear Power Company,Ningde 355200,China;Department of Aerospace Engineering,Nanjing University of Aeronautics and Astronautics,Nanjing 210016,China)
出处 《热力发电》 CAS 北大核心 2018年第10期142-146,共5页 Thermal Power Generation
关键词 核电汽轮机 凝汽器 半侧运行 流体弹性激振 疲劳断裂 流体激励 管束振动响应 nuclear steam turbine condenser half-side operation fluid elastic excitation fatigue fracture fluid excitation vibration response of the tube bundle
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  • 1杨振国.核电装置换热器的失效分析及其解决对策[J].金属热处理,2007,32(z1):28-35. 被引量:6
  • 2陈开惠,陈国平,陈健,田致敏,林俊明.核电站凝汽器钛管的涡流在役检测[J].无损检测,1995,17(3):79-80. 被引量:4
  • 3陈明辉,厉日竹,何晓艳,刘俊强.一体化核反应堆套管管束式换热器设计与试验[J].清华大学学报(自然科学版),2006,46(12):2065-2068. 被引量:4
  • 4(日)上原春男 朱永荃(译).表面式凝汽器的总体传热系数的热力计算[J].电站辅机,1984,(1):21-34.
  • 5王延博.岭澳核电有限公司1、2号机组振动调试工作报告[R].西安:国电热工研究院,2002..
  • 6DETERMINATION OF GLAND SETING COMPENSATION FOR DISTORTED CYLINDERS[R]. ALSTOM,2001.
  • 7中国动力工程学会.火力发电设备技术手册:第二卷,汽轮机[M].北京:机械工业出版社,2002..
  • 8YANG Z G, GONG Y, YUAN J Z. Failure analysis of leakage on titanium tubes within heat exchangers in a nuclear power plant, Part Ⅱ: Mechanical degra- dation[J]. Materials and Corrosion, 2012,63 ( 1 ) : 18 -28.
  • 9GONG Y, YAO C, YANG Z G, et al. Acidic/Caustic alternating corrosion on carbon steel pipes in heat ex- changer of ethylene plan[J]. Materials and Corro- sion, 2011,62(10) : 967 - 978.
  • 10GB/T3620.1-2007钛及钛合金牌号和化学成分[S].北京:中国标准出版社,2007.

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