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The characterization of electrodeposited chromium barriers for nuclear reactor cladding application
Journal of Nuclear Materials ( IF 3.1 ) Pub Date : 2019-12-30 , DOI: 10.1016/j.jnucmat.2019.151980
Sunghwan Yeo , Jun Hwan Kim , Sung Ho Eom

A layer of Cr coating on the inner surface of HT9 cladding is a promising barrier to hinder fuel and cladding chemical interaction (FCCI) in sodum-coolded fast reactors (SFRs). Cr barriers obtained with various current densities and electrolyte temperatures used for the electrodeposition of HT9 disks, were investigated for thickness, Vickers hardness, and the existence and length of microcracks. The crack-free Cr barrier electrodeposited at 1.6 A/cm2 and 80 °C for 70 min showed excellent barrier performance in the diffusion couple test with Ce/Nd alloy at 580 °C for 25 h. These conditions were applied to the electrodeposition of HT9 cladding tubes. The Cr barrier with a thickness of 27.24 ± 1.25 μm having sound microstructure was successfully coated on the inner surface of HT9 cladding tubes using a developed electrodeposition system for the tubes. Burst and tensile mechanical tests verified the excellent adhesion and ductile characteristics of the Cr barriers.



中文翻译:

核反应堆熔覆应用中电沉积铬阻挡层的表征

HT9覆层内表面上的一层Cr涂层是有希望成为阻碍钠冷快堆(SFR)中燃料和覆层化学相互作用(FCCI)的屏障。研究了在不同电流密度和电解质温度下用于HT9圆盘电沉积的Cr阻挡层的厚度,维氏硬度以及微裂纹的存在和长度。以1.6 A / cm 2电沉积无裂纹的Cr阻挡层在Ce / Nd合金在580°C的条件下进行25 h的扩散偶合测试时,在80°C和70°C的条件下表现出优异的阻隔性能。这些条件适用于HT9熔覆管的电沉积。使用开发的电沉积系统,将具有良好微观结构的,厚度为27.24±1.25μm的Cr阻挡层成功地涂覆在HT9包层管的内表面上。爆炸和拉伸机械测试证明了Cr阻挡层具有出色的附着力和延展性。

更新日期:2019-12-30
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