国产Incoloy—800合金U形样管通过技术鉴定

<正> 我国第一座30万kW核电站(秦山电厂)蒸汽发生器用的U形传热管是从瑞典山特维克公司进口的外表面经喷丸处理的lncoloy一800合金管。为加快实现核电站蒸汽发生器用U形管的国产化,自1983年以     

EPR与CPR1000核电站波动管焊接差异分析

通过对EPR与CPR1000核电站波动管安装技术要求、施工逻辑顺序及焊接过程的详细对比分析,阐明了两者的异同,为核电站主回路系统波动管的安装提供了重要的参考。     

800合金U型管表面喷丸工艺的研究与实践

表面喷丸是生产800合金U型蒸汽发生器传热管成品必不可少的处理工序。介绍了上海五钢（集团）有限公司研制的喷丸设备特点,并对喷丸工艺进行了研究、实践表明,研制的设备和试验工艺可行;喷丸管的各项指标符合技术条件,与瑞典管基本一致。     

核电用管现状及国产化进展

随着我国大型核电站建设的快速发展,核电站设备国产化进程明显加快,对核电用无缝钢管的国产化要求也日益迫切。简介了核电用管的特点及质量要求,分析了核电站管道系统用无缝钢管的国产化进展和存在的问题,提出了核电用无缝钢管全部国产化的建议和改进思路。     

核电站反应堆冷却剂系统波动管安装焊接技术

论述了核电站反应堆冷却剂系统波动管的安装、焊接技术,详细阐述了波动管安装前的方案、焊接工艺评定等的准备工作要求,安装工序和具体实施过程及要点,焊接技术要求和焊接参数控制,焊接质量检验方法以及焊接变形的控制等,并对波动管焊接工作的重点进行了经验总结和反馈,对后续核电站反应堆冷却剂系统波动管的安装焊接及质量控制具有借鉴作用...     

核电站核岛EM9仪表管安装及焊接质量控制

文中通过对核电站核岛电仪部分仪表管的安装技术要求分析,按照不同的母材材质和管径制订相应的焊接工艺评定,并按照焊接工艺评定的覆盖范围开展仪表管的安装和焊接。结果表明：按照标准要求所开展的焊接工艺评定无损检验和理化检验结果合格,按照焊接工艺评定的覆盖范围开展核电厂核岛仪表管道的焊接满足仪表管的安装技术要求,为核电站其他同类型管道安装和焊接质量控制提供参考和借鉴。     

核电站用管的生产及发展前景

简要介绍了世界核电站的发展现状及核电站用管情况,重点介绍了核电站蒸发器用管的生产特点及生产工艺。     

攀成钢开始大批量规模生产核电用管

<正>因为核电是无碳能源,因此核电在我国发展战略中具有特殊地位。当前和今后一段时间我国将建设数量可观的核电站,核电建设的用钢量也将大幅增加,其中管道用钢不仅数量大,且质量要求十分高。过去我国核电建设的管道全部仰赖进口,随着岭澳二期核电站常规岛用管首次采用国产钢管后,我国核电建设用管进入国产化阶段。     

EPR核电站波动管安装及焊接

对EPR核电站波动管的安装技术要求、施工逻辑顺序及焊接过程进行了详细分析。分析结果表明:EPR核电站波动管的安装在施工逻辑上安装逻辑顺序单一;焊接采用窄间隙自动焊方法进行焊接,窄间隙坡口设计具有减小焊接残余应力和变形,提高焊接质量,减少焊接材料填充量,降低生产成本的优点;同时采用自动焊技术摆脱了焊工技能水平的影响,提高了波动管现场焊接的质量和生产效率。     

核电站蒸汽发生器管板锻件热处理质量控制研究

以某百万千瓦级核电站蒸汽发生器管板锻件的生产为例,针对管板锻件的特点,研究热处理工序中影响产品质量的主要因素,系统地分析如何控制其热处理过程的关键环节,从而获得满足产品使用要求的优质产品.     

核电站控制棒驱动机构驱动杆用1Cr13厚壁管材成分选择与工艺优化

通过优化设计与控制C,Ni,Cr主合金元素和H,O,N气体元素含量,优化管材冷轧工艺,有效防止了1Cr13管材加工时的开裂现象,保证了管材表面质量良好;通过调整成品热处理工艺,使试制的管材样件的力学性能完全满足了技术条件要求.     

Fe-Cr-Ni合金碱性应力腐蚀破裂

介绍了核电站蒸汽发生器传热管Fe-Cr-Ni合金，特别是800合金的碱性应力腐蚀破裂,总结了材质成分，热处理，应力，冷加工，环境和电化学等因素对Fe-Cr-Ni合金的碱性应力腐蚀破裂的影响，并归纳了预测应力腐蚀破裂敏感电位的方法。     

STUDY OF HOT CORROSION RESISTANCE MECHANISMS OF ARC SPRAYING COATINGS

１ＩｎｔｒｏｄｕｃｔｉｏｎＴｈｅｃｏｒｒｏｓｉｏｎｐｒｏｔｅｃｔｉｏｎｏｆｉｎｄｕｓｔｒｙｂｏｉｌｅｒｔｕｂｅｓｉｓａｎｉｍｐｏｒｔａｎｔｅｃｏｎｏｍｉｃｐｒｏｂｌｅｍ．Ｔｈｅｈｏｔｃｏｒｒｏｓｉｏｎｏｆｂｏｉｌｅｒｔｕｂｅｓｔｈｒｅａｔｅｎｓｓｅｒｉｏｕｓｌｙｔｈｅｓｅｃｕｒｉｔｙｏｐｅｒａｔｉｏｎｏｆｐｏｗｅｒｓｔａｔｉｏｎ．Ｃｕｒｒｅｎｔｌｙ,ｓｏｍｅｃｏｕｎｔｒｉｅｓｄｅａｌｗｉｔｈｔｈｉｓｐｒｏｂｌｅｍｂｙｔｈｅｒｍａｌｓｐｒａｙｔｅｃｈｎｏｌｏｇｙａｎｄａｃｈｉｅｖｅｇｏｏｄｒｅｓｕ…     

热交换器传热钛管的涡流检测及失效分析

利用涡流检测技术,对某核电站泄漏的热交换器用传热钛管进行抽样检测;结合其工作环境,分析其失效形式.结果表明,热交换器内壁防腐橡胶脱落导致异物堵塞和冲刷腐蚀是导致钛管失效的主因;海水流速过高和附近海域泥砂含量过大是导致钛管失效的根本原因.最后对该电厂钛管的防护提出解决方案.     

Corrosion behavior for Alloy 690 and Alloy 800 tubes in simulated primary water

Corrosion behavior for Alloy 690 and Alloy 800 in simulated primary water is studied by open-circuit potential (OCP) measurement, electrochemical impedance spectroscopy (EIS) and potentiodynamic polarization. Rise of pressure and temperature lead to negative shift of corrosion potential for both Alloy 690 and Alloy 800. EIS results show that the effect of pressure on corrosion only exists in low-frequency region, while the effect of temperature presents at the entire frequency range. Alloy 690 shows a better corrosion resistance than Alloy 800 at present investigated conditions.     

Qualifizierung metallischer Werkstoffe für die Eindampfung von Abwässern aus der Rauchgasentschwefelung

Qualification of metallic materials for evaporation of waste water from flue gas desulfurization plants The ecologically-minded processing of waste water from the wet scrubbing of flue gases of coal-fired power plants to produce environmentally acceptable products is carried out in a two-step evaporater operating in closed loop mode. The evaporating process leads to high concentration of chlorides in the two evaporation steps: up to about 100 g/l in the 1st step and up to about 350 g/l in the 2nd step. Therefore in case of metallic design of the evaporation equipment materials of construction with exceptional resistance to chloride induced pitting are required. The corrosion resistance of the high-alloyed stainless steel Alloy 31 (X1NiCrMoCu32-28-7 – UNS N 08031) and of the NiCrMo-alloys Alloy C-276 (NiMo16Cr15W – UNS N 10276) and Alloy 59 (NiCr23Mo16Al – UNS N 06059) including their weldments were to be tested for this application both in the laboratory and in field tests. In addition the behaviour of Alloy 59 heat exchanger tubes had to be determined in field tests under heat-transfer service conditions. The critical pitting corrosion temperatures of the 3 materials after having been GTAW welded under uniform conditions with FM 59 (ERNiCrMo–12) filler were determined in potentiostatic tests in model solutions imitating concentrated waste water products as they may occur in practice, using 5 K temperature intervals. As to be expected the critical corrosion resistance limits of the materials lie at 85 °C at chloride concentrations of 100 g/l Cl⁻ for the Alloy 31 and of 300 g/l Cl⁻ for both the Alloy 59 and the Alloy C–276 respectively. Field tests in waste water evaporation units of flue gas desulfurization plants of coal-fired power stations are carried out as immersion tests with the welded materials and as heat-exchange experiments using longitudinally welded tubes of Alloy 59 (2.4605). The immersion tests over a period of 32 months show the Alloy 31 (1.4562) to be a corrosion resistant construction material for tubes and containers in the first evaporation step, whereas the Alloy 59 (2.4605) and the Alloy C–276 (2.4819) have to be used for the second evaporation step, where the chloride contents are much higher. The Alloy 59 is to value as the most resistant material according to its lower tendency to crevice corrosion. The heat-exchange experiments over a test period of 9 months cause to expect the Alloy 59 to be a suitable construction material for heat-exchanger tubes in both evaporation steps in comparison to graphite which is more succeptible to mechanical destroying.     

Corrosion resistance of SG tubing material Incoloy 800 mod. and Inconel 690 TT

The corrosion resistance of the SG tubing material Incoloy 800 mod. and Inconel 690 TT is considered with respect to pitting, sensitization characteristics and stress corrosion cracking, especially chloride-induced cracking, pure water cracking and caustic cracking. Based on laboratory data Incoloy 800 mod. as well as Inconel 690 TT show very good corrosion resistance under specified and faulted SG water conditions. The published results often refer to Incoloy 800 according to ASTM B 163–66. It is shown that the Incoloy 800 grade used by nuclear power suppliers is optimized for this application. The restricted chemical composition of the modified grade of Incoloy 800 vs. the standard grade is discussed and it is shown that this results in a significantly higher resistance to the above mentioned corrosion phenomena. The operating experience with Incoloy 800 mod. heat transfer tubes in nuclear steam generators is discussed briefly with respect to corrosion. No materrial-specific weaknesses have been observed with Incoloy 800 mod. Since more than 19 years of operation only at one tube out of 235 000 SG tubes made of Incoloy 800 mod. a leakage caused by corrosion has been occurred. This finding is independent of different tube manufacturers and different water treatments of the various plants.     

日本电站锅炉用奥氏体不锈钢管及合金管的发展

日本为提高发电效率，电站锅炉蒸气条件已由超临界压向超超临界压发展，为满足需要，在现有奥氏体不锈钢管的基础上，改进和新研制出奥氏体不锈钢管及其合金管以及合会复合管。     

精轧管管坯准备的工艺试验

介绍了承德钢铁股份有限公司钢管厂利用现有生产设备,以冷拔方式为精轧管提供管坯的生产工艺试验方案及试验过程。通过三种工艺试验效果的比较分析,确定了一种能满足精轧管管坯要求的较为合理的生产工艺。     

Double loop electrochemical potentiokinetic reactivation test of Nickel-base Alloy 600 surface-melted by a CO2 laser beam

Ni-base Alloy 600 has been widely used as a steam generator (S/G) tubing material in nuclear power plants because of its good mechanical and corrosion properties at high temperatures. However, degradations of S/G tubes due to intergranular attack (IGA) and intergranular stress corrosion cracking (IGSCC) during normal operation have been frequently reported. In particular, Alloy 600 can be very susceptible to IGA/IGSCC in some sulfur-bearing environments by sensitization. In this paper, the beneficial effects of laser surface melting (LSM) on intergranular corrosion of the sensitized Alloy 600 is presented from the results of the double loop electrochemical potentiokinetic reactivation (DL-EPR) test. The DL-EPR test was performed in de-aerated 0.01 M H₂SO₄+20 ppm KSCN at a scan rate of 0.5 m V/sec at room temperature. The degree of sensitization (DOS) of the sensitized Alloy 600 measured from the DL-EPR test was considerably reduced by LSM. The sensitized Alloy 600 after LSM also exhibited a relatively low DOS, compared with that of the sensitized but not laser treated Alloy 600. From the microscopic observation, it was found that the microstructural changes brought about by the LSM process, especially changes in the precipitation behavior of grain boundary Cr-rich carbides, caused the improvement of resistance to intergranular corrosion of the laser treated Alloy 600. The resistance to IGSCC of the laser treated Alloy 600 in sulfur-bearing environments was also discussed from the results of measured DOS and microstructural examination. This article based on a presentation made in the symposium “The 4th International Conference on Fracture and Strength of Solid”, held at POSTECH, Pohang, Korea, August 16–18 under the auspices of Far East and Ocean Fracture Society (FEOFS),et al.