首页> 外文会议>International conference on environmental degradation of materials in nuclear power systems-water reactors >IN-SITU IRRADIATION ACCELERATED OXIDATION OF ZIRCALOY-4 UNDER PROTON OR ELECTRON IRRADIATION IN PWR PRIMARY WATER
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IN-SITU IRRADIATION ACCELERATED OXIDATION OF ZIRCALOY-4 UNDER PROTON OR ELECTRON IRRADIATION IN PWR PRIMARY WATER

机译:压水堆原水在质子或电子辐照下ZIRCALOY-4的原位辐照加速氧化

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Corrosion experiments on Zircaloy-4 were conducted in-situ in simulated PWR primary water (320°C water with 3 wt. ppm H_2 without Li and B addition) during irradiation with 3.2 MeV protons or with 1.5 MeV electrons to isolate the effect of displacement damage. The Zircaloy-4 foil acted as a "window" to allow protons/electrons to fully penetrate and deposit their energy in water to induce radiolysis. The area of the samples exposed to the proton beam experienced both displacement damage and radiolysis, while the sample exposed to electron beam was only affected by radiolyzed water. The aim of the study is to characterize the effect of radiation on the kinetics and character of oxidation caused by accelerated waterside corrosion under irradiation. Samples irradiated with protons for total displacement damage of 0.14 dpa (damage rate at 4.4× 10~(-7) dpa/s in metal, and 400 kGy/s in the water) at an exposure time of 24 h in water was compared with electron-irradiated samples (~400 kGy/s in water) in the same condition, and with unirradiated corrosion samples. Results show that the sample area exposed to proton irradiation had an oxidation rate about 10 times that of the unirradiated area, whereas electron irradiated sample had no apparent enhanced corrosion area. Oxide morphology and phase structure were investigated using TEM and Raman spectroscopy. The unirradiated oxide consisted mainly of larger columnar monoclinic ZrO_2 grains, while the proton irradiated oxide exhibited a smaller equiaxed monoclinic ZrO_2 grain structure. The electron irradiated oxide maintains its columnar monoclinic ZrO_2 grain structure.
机译:在3.2 MeV质子或1.5 MeV电子辐照下,在模拟PWR初级水(320°C的水,含3 wt。ppm H_2,不添加Li和B的水中)中对Zircaloy-4进行腐蚀实验,以隔离位移的影响损害。 Zircaloy-4箔片充当“窗口”,以允许质子/电子完全渗透并将其能量沉积在水中以引发放射分解。暴露于质子束的样品区域经历了位移损伤和辐射分解,而暴露于电子束的样品仅受到放射性水的影响。该研究的目的是表征辐射对辐射作用下加速的水边腐蚀引起的动力学和氧化特性的影响。将质子辐照的样品在水中暴露24 h时的总位移损伤为0.14 dpa(金属中4.4×10〜(-7)dpa / s的损伤率,水中400 kGy / s的损伤率)与电子辐照样品(在水中约400 kGy / s)处于相同条件下,并且未辐照腐蚀样品。结果表明,暴露于质子辐照下的样品区的氧化速率约为未辐照区的10倍,而电子辐照样品的氧化区则没有明显增加的腐蚀面积。使用TEM和拉曼光谱研究了氧化物的形态和相结构。未辐照的氧化物主要由较大的柱状单斜ZrO_2晶粒组成,而质子辐照的氧化物具有较小的等轴单斜ZrO_2晶粒结构。电子辐照的氧化物保持其柱状单斜ZrO_2晶粒结构。

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