Influence of Neutron Irradiation on Mechanical Properties of Cr-coated Zirconium Alloy
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摘要: 为研究中子辐照对Cr涂层锆合金力学性能的影响，获得Cr涂层锆合金的辐照性能数据，本文针对多弧离子镀技术制备的Cr涂层锆合金开展了中子辐照考验，通过拉伸试验过程实时观测试样力学行为变化并对试验后断口微观形貌进行分析，研究了辐照后Cr涂层锆合金的力学性能以及涂层与基体的结合能力。结果表明：中子辐照导致Cr涂层锆合金的抗拉强度和屈服强度升高，断后伸长率下降，表现出与商用锆合金相似的辐照强化效应。同时Cr涂层与无涂层锆合金相比，其屈服强度和抗拉强度升高但塑性变形能力降低。另一方面，Cr涂层在拉伸变形量较大时产生环向裂纹，但未从基体表面剥落，中子辐照未对涂层结合强度产生明显的影响，受力过程中涂层仍保持了完整性。Abstract: In order to study the influence of neutron irradiation on the mechanical properties of Cr-coated zirconium alloy, a neutron irradiation test is carried out in this paper for the Cr-coated zirconium alloy prepared by multi-arc ion plating technology. The mechanical properties were conducted by in situ tensile tests and the coating adhesion was analyzed by micron morphology characterization. Results show that Cr coating zircaloy has a similar irradiation effect with commercial zircaloy cladding. Compared with uncoated zircaloy, Cr coating shows that the yield strength and tensile strength increased but percentage elongation after fracture decreased．The Cr coating shows cracks till a large tensile strain without peeling off before rupture. The Cr coating exhibits good mechanical properties and excellent adhesion with Zircaloy Tubes.
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图 1 带涂层和无涂层锆合金的拉伸工程应力-应变曲线
Figure 1. The Stress-Strain Curves of Uncoated and Coated Zirconium Alloys
图 2 拉伸试验全过程Cr涂层宏观形貌变化
Figure 2. Macro-morphological Changes of Cr Coating throughout the Tensile Test
图 3 未辐照Cr涂层锆合金试样的拉伸断裂微观形貌
Figure 3. Tensile Fracture Micromorphology of Unirradiated Cr-coated Zirconium Alloy Sample
图 4 辐照后Cr涂层锆合金试样的拉伸断裂微观形貌
Figure 4. Tensile Fracture Micromorphology of Irradiated Cr-coated Zirconium Alloy Sample
图 5 辐照前后Cr涂层锆合金试样的EDS分析结果
Figure 5. EDS Analysis Results of Cr-coated Zirconium Alloy Sample before and after Irradiation
表 1 Cr 涂层锆合金拉伸性能数据
Table 1. Tensile Property Data of Cr-coated Zirconium Alloy
状态 屈服强度Rp0.2/MPa 抗拉强度Rm/MPa 断后伸长率A100/% 无涂层未辐照 359 539 31 带涂层未辐照 384 548 25 无涂层辐照后 715 855 9 带涂层辐照后 787 904 3 
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