期刊文献+

超临界水冷堆候选材料蠕变性能研究

Study on Creep Property of Candidate Material for SWCR
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摘要 采用RDL50型蠕变持久试验机研究316Ti、347、HR3C和6XN四种奥氏体不锈钢和718、825、800H三种高温合金在550~700℃,65-120 MPa范围内几种条件下的蠕变性能。 Thc creep property four austenitic stainless SteelS (316Ti, 347; HR3G and 6XN) and three high temperature alloys (718. 825, 800H/ was investigated with Creep testing machine RDL50 under several conditions within the range of 550-700 ℃ and 65L120 MPa.
出处 《一重技术》 2013年第2期49-52,共4页 CFHI Technology
关键词 超临界水冷堆 蠕变 奥氏体不锈钢 高温合金 supercritical water cooled reactor(SWCR) creep austenitic stainless steel high temperature alloy
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参考文献5

  • 1G S Was, P Ampornrat, G Gupta, et al Cracking in Supercritical Water [J] 2007, 371 (1-3): 176-201.
  • 2Corrosion and Stress Eorrnsiun Journal of Nuclear Materials, T Schulenburg, J Starflinger, P Marsault, et al. European Supercritical Water Cooled Reactor [J| . Nuclear Engineering and Design, 2011, 241 (9): 3505-3513.
  • 3T C Totemeier, D E Clark. Effeet of Transient Thermal Cycles in a Supereritical Water-cooled Reactor on the Microstructure and Properties of Ferritic-Martensitic Steels [J] . Journal of Nuclear Materials, 2006, 355:104-113.
  • 4Chunwen Sun, Rob Hui, Wei Qui, et al. Progress in Corrosion Resistant Materials for Supercritical Water Reactors [J] . Corrosion Science, 2009, 51 (11): 208-252.
  • 5L K Mansur, A F Rowcliffe, R K Nanstad, et al. Materials Needs for Fusion, Generation IV Fission Reactors anti Spallation Neutron Sources-similarities and Differences I J] . Journal of Nuclear Materials, 2004, 329-333: 166-172.

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