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Iodine-Induced Stress Corrosion Cracking of Zircaloy-4: Identification of Critical Parameters Involved in Intergranular to Transgranular Crack Propagation

机译:锆诱导的锆石英 - 4的应力腐蚀裂解:识别晶间裂纹传播中涉及的关键参数

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During power transient conditions in nuclear reactors, uranium oxide pellets expand and crack due to the increase in temperature and their poor thermal conductivity. Moreover, the cladding undergoes creep because of the external pressure, and its diameter shortens. These antagonistic phenomena lead to the establishment of a contact between the pellet and the cladding, called the pellet-cladding interaction. The synergistic effect of the hoop tensile stress and strain imposed on the cladding by fuel thermal expansion and corrosion by iodine released from the UO_2 fuel as a fission product at the same time can lead to Iodine-induced Stress Corrosion Cracking (I-SCC) of the Zircaloy-4 cladding. I-SCC failures of zirconium alloys are usually described in three steps: initiation of cracks, intergranular subcritical propagation, and critical propagation with a brittle transgranular propagation mode [1]. Transgranular propagation occurs as soon as the stress intensity factor overshoots a threshold value K_(I, SCC). It is the critical step and leads to the final ductile failure of the cladding. Transgranular cracks propagate by cleavage-like fracture on basal planes of the hexagonal lattice and fluting; it is the result of a competition between a plastic accommodation of the applied strain and the brittle fracture of basal planes by iodine assisted cleavage. Several environmental, mechanical and microstructural parameters can affect each one of the propagation stages. The specimen texture, describing the variation in preferential orientation of the c-axis, appears to be one of the main controlling parameters for transgranular propagation in unirradiated zirconium alloys [1]. Strain-hardening has also been reported as a factor enhancing transgranular propagation of I-SCC cracks [2]. However, strain-hardening includes several parameters such as local internal stresses, grain reorientation, twinning or activation of different slip systems. Each one of those parameters may enhance transgranular cracking, but synergistic effects and critical parameters have not been identified yet. In that context, the purpose of this study is to progress in the identification of critical factors enhancing transgranular propagation of cracks. A strain-hardening pre-treatment is applied on Zircaloy-4 samples, using various elongations and strain rates. Resulting microstructures are characterized by transmission electron microscopy (TEM) with attention paid to respective activation of twinning and slip modes. Internal stresses are evaluated. Pre-strained or as-received tensile Zircaloy-4 specimens are tested under constant load, in presence of iodine methanol solution at room temperature. Fractographic observations carried by scanning electron microscopy (SEM) and TEM observations of grains passed by cracks (intergranular propagation) or crossed by cracks (transgranular propagation) help discussing results.
机译:在核反应堆的电力瞬态条件下,氧化铀颗粒由于温度的增加和其导热性差而导致膨胀和裂纹。此外,由于外部压力,包层经历蠕变,直径缩短。这些拮抗现象导致在颗粒和包层之间建立接触,称为颗粒包层相互作用。同时通过UO_2燃料从UO_2燃料中释放的燃料热膨胀和腐蚀施加在包层上施加在燃料热膨胀和腐蚀的协同效应可以导致碘诱导的应力腐蚀裂纹(I-SCC)锆石 - 4包层。锆合金的I-SCC故障通常用三个步骤描述:启动裂缝,晶间亚临界传播和具有脆性转弦传播模式的临界传播[1]。一旦应力强度因子过冲了阈值k_(i,scc),就会发生跨血管传播。这是关键步骤,导致包层的最终延性失效。旋转裂缝在六边形晶格的基础平面上通过裂解状裂缝繁殖;它是碘辅助裂解塑性菌株的塑料容纳与基底平面脆性骨折之间的竞争的结果。几种环境,机械和微结构参数可以影响每个传播阶段。描述C轴优先取向的变化的样本纹理似乎是未照射锆合金中的跨凝血繁殖的主要控制参数之一。还报告了应变硬化作为增强I-SCC裂缝的转晶繁殖的因子[2]。然而,应变硬化包括若干参数,例如局部内部应力,晶粒重新定位,孪晶或不同滑动系统的激活。这些参数中的每一个可以增强跨凝血裂缝,但尚未识别协同效应和临界参数。在这种情况下,本研究的目的是在鉴定提高裂缝转晶繁殖的关键因素的识别。使用各种伸长率和应变速率,对锆丙酰-4样品施加应变硬化预处理。产生的微观结构的特征在于透射电子显微镜(TEM),注意到孪生和滑动模式的各自激活。评估内部应力。在室温下在碘甲醇溶液存在下,在恒定负荷下在恒定载荷下进行预束或接收的拉伸锆醇-4样品。通过扫描电子显微镜(SEM)和由裂缝(晶间繁殖)通过的晶粒(晶体繁殖)或通过裂缝(跨缩繁殖)交叉的晶粒(转晶繁殖)通过裂缝(转晶繁殖)通过析出结果。

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