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奥氏体不锈钢在超临界水环境中的应力腐蚀开裂性能研究

DOI: 10.11903/1002.6495.2013.129, PP. 143-148

Keywords: 超临界,慢应变速率拉伸,应力-应变曲线,延伸率,应力腐蚀开裂倾向

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Abstract:

利用慢应变速率拉伸(SSRT)的方法研究了奥氏体不锈钢AL-6XN,316Ti和TP-347在550/650℃,25MPa的超临界水环境中的应力腐蚀开裂敏感性。结果表明,随着温度由550℃升高到650℃,其屈服强度和抗拉强度均发生了明显的下降,而三者的延伸率却呈现出了3种不同的变化规律。由试样的断口和侧面形貌可知,AL-6XN在550/650℃,316Ti在550℃工况下具有应力腐蚀开裂倾向,且其应力腐蚀开裂倾向大小关系为AL-6XN/550℃>316Ti/550℃>AL-6XN/650℃。

References

[1]  Zhang L F, Bao Y C, Tang R. Selection and corrosion evaluation tests of candidate SCWR fuel cladding materials [J]. Nucl. Eng. Des., 2012, 249: 180
[2]  李红梅, 蔡珣, 吕战鹏等. 304不锈钢在含硼和锂的高温水中的应力腐蚀破裂和表层氧化膜分析 [J]. 材料工程, 2004, (4): 7
[3]  Gupta G, Ampornrat P, Ren X, et al. Role of grain boundary engineering in the SCC behavior of ferritic-martensitic alloy HT-9 [J]. J. Nucl. Mater., 2007, 361: 160
[4]  Was G S, Ampornrat P, Gupta G, et al. Corrosion and stress corrosion cracking in supercritical water [J]. J. Nucl. Mater., 2007, 371(1-3): 176
[5]  Kilian R, Hoffmann H, llg U, et al. Environmental degradation of materials in nuclear power systems-water reactors [A]. Proc. 12th Int. Conf [C]. USA, TMS: 2005, 803
[6]  Kritzer P. Corrosion in high temperature and supercritical water and aqueous solutions: A review [J]. J. Super. Fluids, 2004, 29: 1
[7]  Sridharan K, Zillmer A, Licht J R, et al. Corrosion behavior of candidate alloys for supercritical water reactors [A]. Proc. ICAPP'04 [c]. Pittsburgh P A, USA: 2004: 4136

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