核电站蒸汽发生器热交换器管用奥氏体钢和合金的局部腐蚀

L. A. Pisarevskii, A. B. Korostelev, A. Lipatov, G. Filippov, T. Kin
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引用次数: 2

摘要

研制与未来反应堆热载体接触的耐腐蚀性能更高的现代国产结构材料是核电工程创新项目开发中的一个重要问题。换热管是影响蒸汽发生器安全可靠运行的关键部件。研究了奥氏体类非稳定含氮耐蚀钢经冷变形、热处理和长期热时效后的腐蚀性能。结果表明,在氮钼合金铬镍钢中引入硅,可提高其抗局部腐蚀性能,并将其与低碳钢和合金的抗晶间腐蚀和点蚀性能联系起来。但是,在热载体温度为450-500°С的试验性03Х18Н13С2АМ2ВФБР-Ш低碳微合金钢,在360°С及更高的温度下长期热老化后,其抗局部腐蚀和抗冲击性有下降的趋势。目前,为了防止换热管性能的退化,对生产工艺参数进行了规定,对合金元素含量进行了平衡。与316LN和08Х18Н10Т钢种相比,03Х17Н13С2АМ2钢种具有更高的抗局部腐蚀性能和强度,可作为生产水-水型核电机组蒸汽发生器换热管的候选材料。提出了抗高氧化介质中晶间腐蚀的新型03Х17Н9АС2钢,用于替代10Х15Н9С3Б1-Ш (ЭП 302-Ш)钢与铅热载体接触条件下的运行试验。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Local corrosion of austenitic steels and alloys for heat exchanger tubes of nuclear power stations steam generators
Elaboration of modern domestic structural materials with increased corrosion resistance in contact with advanced heatcarriers of future reactor plants is an important problem at development of innovation projects of nuclear power engineering. Heatexchanging tubes are the critical components, which influence on the safety and reliability of steam generators operation. Corrosion properties of non-stabilized nitrogen-containing corrosion resistant steels of austenite class after cold deformation, thermal treatment and long-term thermal aging studied. It was shown, that silicon introducing into chrome-nickel steel, alloyed by nitrogen and molybdenum, results in increasing of its resistance against local kinds of corrosion and equated it on resistance against intercrystallite and pitting corrosion with particularly low-carbon steels and alloys. But the experimental 03Х18Н13С2АМ2ВФБР-Ш low carbon micro-alloyed steel, proposed for operation at a heat-carrier temperature of 450–500 о С, in the first version had a tendency to a decrease of resistance against local corrosion and impact resistance after long-term thermal aging at temperatures of 360 о С and higher. At present specifying of technological parameters of production and balanced alloying element content takes place, which prevents heat exchanging tubes properties degradation. Steel 03Х17Н13С2АМ2 which has higher resistance against local corrosion and strength comparing with 316LN and 08Х18Н10Т grades, can be taken as a candidate material for production of heat-exchanging tubes of steam generators of nuclear power stations having power reactors of water-water type. The new 03Х17Н9АС2 steel, resistant against inter-crystallite corrosion in high-oxidizing media, was proposed for tests of its operation under conditions of contact with lead heat-carriers instead of 10Х15Н9С3Б1-Ш (ЭП 302-Ш) steel.
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