首页> 外文会议>ICONE18;International conference on nuclear engineering >THERMAL AGEING EMBRITTLEMENT OF CASTING DUPLEX STAINLESS STEELS FOR NUCLEAR POWER PLANT
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THERMAL AGEING EMBRITTLEMENT OF CASTING DUPLEX STAINLESS STEELS FOR NUCLEAR POWER PLANT

机译:核电站双相不锈钢铸件的热老化处理

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Cast duplex stainless steels (CSS) used for PWR pipes are degraded due to thermal ageing embrittlement during long-term service at 288 V to 327 V. Z3CN20-09M Cast duplex Stainless Steels (CSS )made in France for domestic nuclear power plants were thermally aged at 400 °C for 100 h, 300 h, 1000 h, 3000 h and 10000 h. The tensile properties and the impact properties at different thermal aging duration were measured and the effects of the thermal aging time on the microscopic structures and substructures of Z3CN20-09Mwere respectively investigated by optical microscopy and transmission electron microscopy. The results showed that the tensile strengths of Z3CN20-09M CSS increased gradually with the increment of the thermal ageing time, whereas the impact properties decreased with the prolonging of the thermal ageing time. After long thermal ageing time the dislocation configurations were greatly changed in austenite, and there were precipitates along the austenite-ferrite interface. Moreover, the iron-rich a phase and the chromium-rich a' phase precipitated in ferrite aged for lOOOOh by nucleation and growth rather than the spinodal decomposition. All of above revealed that Z3CN20-09M CSS became brittle during thermal ageing.
机译:在288 V至327 V的长期使用过程中,由于热老化脆化,用于PWR管道的铸造双相不锈钢(CSS)退化。Z3CN20-09M法国制造的用于国内核电站的铸造双相不锈钢(CSS)是热加工的在400°C下老化100小时,300小时,1000小时,3000小时和10000小时。通过光学显微镜和透射电子显微镜分别测量了在不同热老化时间下的拉伸性能和冲击性能,并研究了热老化时间对Z3CN20-09M微观结构和亚结构的影响。结果表明,Z3CN20-09M CSS的抗拉强度随着热老化时间的增加而逐渐增加,而冲击性能随热老化时间的延长而降低。经过长时间的热时效处理后,奥氏体中的位错构型发生了很大变化,并且在奥氏体-铁素体界面上出现了析出物。而且,通过成核和生长而不是旋节线分解,富铁a相和富铬a′相在经1000h老化的铁素体中沉淀。以上全部表明,Z3CN20-09M CSS在热老化过程中变脆。

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