用于核电厂蒸汽发生器传热管SCC试验的浓碱高压釜装置

DEVELOPMENT OF EQUIPMENT FOR TEST OF CAUSTIC STRESS CORROSION CRACK (SCC) OF STEAM GENERATOR TUBE IN NUCLEAR POWER STATION

  • 摘要: <正> 一、前言 核电厂蒸汽发生器传热管的应力腐蚀破裂(SCC)至今时有发生,造成很大经济损失。因此,它一直是各核电发展国家所关心的重要问题之一。蒸汽发生器传热管发生SCC的原因与纯水介质中杂质钠离子或氯离子在材料受力部位的浓集作用有关。采用磷酸盐水处理工艺以及冷凝器泄漏是造成二回路系统水质遭到钠离子和氯离子沾污的原因。通常,采

     

    Abstract: In nuclear power station, reactor is often forced to shut down for mainten-ance due to serious stress corrosion crack of steam generator tube. To study thetendency of steam generator tube to SCC, a type of autoclave device for SCCtest in caustic solution is developed. The container fabricated from Nickel withwelding seal is used for placing caustic solution and material specimens. The con-tainer is put in the autoclave, connceted with autoclave outside with pipe, andfilled in with pure argon at 2-3 kg/cm~2. C-type of specimen is used for SCC test. Incoloy 800 alloy specimens withshot peening and without shot peening are tested in 50% (wt) NaOH solution at300℃, and SCC is observed on specimens without shot peening after 200 h expo-sure to above codition. The results show that this autoclave device is reliable and safe in use, it willbe able to meet the needs of caustic SCC testing of materials for steam generatortube in nuclear power station.

     

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