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Fracture toughness evaluation for Zr-4 clad tubing structure with pellet inserts
Theoretical and Applied Fracture Mechanics ( IF 5.0 ) Pub Date : 2020-08-01 , DOI: 10.1016/j.tafmec.2020.102657
Jy-An Wang

Abstract Applying fracture mechanics approach to spent nuclear fuel (SNF) system reliability investigation is warranted due to the inherent flaws and hydride structures existed in a SNF system after nuclear reactor operation. However, none of the existing fracture toughness data deal with fuel cladding specific geometry or spent fuel material conditions, such as cladding structure with the pellet-inserts and the associated pellet clad mechanical interactions induced mixed-mode damage mechanisms. Thus, the development of an intrinsic fracture mechanics approach that is suitable for SNF materials is needed. Due to thin wall and small dimension of clad tubing structure, the spiral notch torsion test (SNTT) method of small specimen approach was used to estimate the clad tubing structure fracture toughness. The estimated fracture toughness for Zr-4 cladding with alumina-pellet inserts are presented in this report. For SNTT samples with a short or medium crack length, between 5.4-mm and 8-mm, the estimate JIQ upon fracture initiation for the baseline Zr-4 cladding is at 50 kJ/m2 with 2-sigma uncertainty of 3.26 kJ/m2, and the associated KIQ is at 67.46 MPa√m. For SNTT samples with a long crack length, around 13-mm, the crack initialization is deviated from that of the Mode-I tensile fracture and appears to be a mixed-mode fracture of Mode I – tensile stress and Mode III – out of plane shear stress; the estimated JMQ is at 18.9 kJ/m2, the associated KMQ is at 41.4 MPa√m.

中文翻译:

带颗粒嵌件的 Zr-4 复合管结构的断裂韧性评估

摘要 由于核反应堆运行后SNF系统存在固有缺陷和氢化物结构,因此将断裂力学方法应用于乏核燃料(SNF)系统可靠性研究是有必要的。然而,现有的断裂韧性数据都没有涉及燃料包壳特定的几何形状或乏燃料材料条件,例如带有芯块插入物的包壳结构和相关的芯块包壳机械相互作用引起的混合模式损伤机制。因此,需要开发一种适用于 SNF 材料的内在断裂力学方法。由于复合管结构壁薄、尺寸小,采用小试件法的螺旋缺口扭转试验(SNTT)方法估计复合管结构的断裂韧性。本报告中介绍了带有氧化铝颗粒嵌件的 Zr-4 覆层的估计断裂韧性。对于具有短或中等裂纹长度的 SNTT 样品,在 5.4-mm 和 8-mm 之间,基线 Zr-4 包层断裂开始时的估计 JIQ 为 50 kJ/m2,2-sigma 不确定性为 3.26 kJ/m2,相关的 KIQ 为 67.46 MPa√m。对于裂纹长度长(约 13 毫米)的 SNTT 样品,裂纹初始化偏离了模式 I 拉伸断裂的初始状态,并且似乎是模式 I - 拉伸应力和模式 III - 平面外的混合模式断裂剪应力;估计的 JMQ 为 18.9 kJ/m2,相关的 KMQ 为 41.4 MPa√m。基线 Zr-4 包层断裂开始时的估计 JIQ 为 50 kJ/m2,2-sigma 不确定性为 3.26 kJ/m2,相关的 KIQ 为 67.46 MPa√m。对于裂纹长度长(约 13 毫米)的 SNTT 样品,裂纹初始化偏离了模式 I 拉伸断裂的初始状态,并且似乎是模式 I - 拉伸应力和模式 III - 平面外的混合模式断裂剪应力;估计的 JMQ 为 18.9 kJ/m2,相关的 KMQ 为 41.4 MPa√m。基线 Zr-4 包层断裂开始时的估计 JIQ 为 50 kJ/m2,2-sigma 不确定性为 3.26 kJ/m2,相关的 KIQ 为 67.46 MPa√m。对于裂纹长度长(约 13 毫米)的 SNTT 样品,裂纹初始化偏离了模式 I 拉伸断裂的初始状态,并且似乎是模式 I - 拉伸应力和模式 III - 平面外的混合模式断裂剪应力;估计的 JMQ 为 18.9 kJ/m2,相关的 KMQ 为 41.4 MPa√m。
更新日期:2020-08-01
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