论文部分内容阅读
核蒸汽发生器中的传热管,因管壁最薄,工作条件十分恶劣,往往由于腐蚀而破裂。新型具有热流表面沸腾工况的腐蚀试验装置,为深入研究传热管在工况条件下的应力腐蚀破裂原因及其解决办法,提供了最新的试验手段,此装置可以用于各种材质及不同加工工艺的传热管的腐蚀筛选,模拟蒸汽发生器局部沸腾浓缩工况下的抗应力腐蚀破裂性能的研究,传热管结构腐蚀敏感部位的局部腐蚀裂性能研究,确定二回路水质中Cl~-和NaOH浓度的控制范围,制订出水质的危险标准。装置的试验与静态高压釜试验相比前进了一大步,使试验条件更加接近于工况条件,与模拟体试验相比也能进行模拟工况试验,但比模拟体试验简单容易、投资少、见效快、小巧灵活、在工程研究上起到很大的作用。
Heat transfer tube in nuclear steam generator, because of the thinnest tube wall, the working conditions are very poor, often due to corrosion and rupture. A new type of corrosion test apparatus with heat flow surface boiling conditions provides the latest experimental means for further studying the causes of stress corrosion cracking of heat transfer tubes under working conditions and their solutions and can be used in various materials and in different ways Corrosion process of the heat transfer tube corrosion simulation steam generator partial boiling concentrated anti-stress corrosion cracking performance research, heat transfer tube structure corrosion sensitive parts of the local corrosion cracking properties of the secondary loop to determine the water quality of Cl ~ - and NaOH concentration control range, to develop a water quality standards. Compared with the static autoclave test, the test of the device is a big step forward, so that the test conditions are closer to the working conditions, and the simulated condition test can be carried out compared with the simulated body test. However, the test is simpler and easier than the simulated body test with less investment , Quick, small and flexible, in engineering research has played a significant role.