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首页> 外文会议>STP 1467; International Symposium on Zirconium in the Nuclear Industry; 20040613-17; Stockholm(SE) >Effect of Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes at the End of Design Life
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Effect of Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes at the End of Design Life

机译：设计寿命结束时辐照对Zr-2.5Nb压力管断裂性能的影响

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摘要

To determine the fracture properties of Zr-2.5Nb pressure tubes irradiated until the end of design life, cantilever beam, curved compact toughness, and transverse tensile samples were prepared from a typical pressure tube and irradiated in the high flux reactor OSIRIS at CEA, Saclay, France. Experiments were conducted on two batches of samples mounted in two irradiation inserts. Each insert held sixteen samples of each type of specimen. The first insert was irradiated to a fluence corresponding to approximately half of the design life in a CANDU reactor. The experimental results were reported in [1]. Samples in the second insert were irradiated for 10.5 years in OSIRIS and received a maximum neutron fluence of 2.61 x 10~(26) n/m~2 (E > 1 MeV), being equivalent to 2.98 x 10~(26) n/m~2 (E > 1 MeV) in a CANDU reactor, i.e., corresponding to ～30 years operation in CANDU reactors at 80% capacity factor. The present report describes the results of tensile, fracture toughness, and Delayed Hydride Cracking (DHC) tests and XRD microstructure analysis from the second batch of specimens. A continuous and gradual evolution in tensile, fracture, DHC properties, and dislocation densities is demonstrated without any evidence of a sudden change following the initial transitient at very low fluence. In the whole high fluence range, there is a very slow rate of increase in c-component dislocation density, strength, and DHC velocity and a slow reduction in elongation and Nb concentration in the β-phase. The a-type dislocation density and fracture toughness remain approximately constant. The results from the second insert of specimens confirm that, following the initial transient at very low fluence, there is little further change in the fracture properties of Zr-2.5Nb pressure tube material. Therefore, material properties behave in a stable and predicable manner to the end of a 30 years design life for CANDU reactor pressure tubes.
机译：为了确定直到设计寿命结束时辐照的Zr-2.5Nb压力管的断裂特性，从典型的压力管中制备了悬臂梁，弯曲致密韧性和横向拉伸样品，并在高通量反应器OSIRIS中于萨克雷（CEA）进行了辐照，法国。对安装在两个辐照插入物中的两批样品进行了实验。每个插入物可容纳每种样品的16个样品。在CANDU反应器中，将第一个插入物辐照至大约相当于设计寿命一半的能量密度。实验结果报道在[1]中。第二个插入物中的样品在OSIRIS中辐照10.5年，最大中子通量为2.61 x 10〜（26）n / m〜2（E> 1 MeV），相当于2.98 x 10〜（26）n /在CANDU反应堆中，m〜2（E> 1 MeV），即在80％容量系数下，相当于CANDU反应堆中运行约30年。本报告描述了第二批样品的拉伸，断裂韧性和延迟氢化物开裂（DHC）测试和XRD微观结构分析的结果。拉伸，断裂，DHC特性和位错密度连续不断地变化，没有任何迹象表明以非常低的通量在初始瞬态之后发生突然变化。在整个高通量范围内，c组分位错密度，强度和DHC速度的增加速率非常缓慢，而β相中的伸长率和Nb浓度则缓慢降低。 a型位错密度和断裂韧性保持大致恒定。样品第二次插入的结果证实，在非常低的注量下进行初始瞬变之后，Zr-2.5Nb压力管材料的断裂性能几乎没有进一步的变化。因此，对于CANDU反应堆压力管，其材料性能以稳定且可预测的方式运行到30年设计寿命结束。

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