锆合金

新锆合金的相变温度

Phase Transition Temperature of the New Zircaloy

我们也放入了燃料大头针，在同样的锆合金的管子里。

And we 'll also be putting the fuel pins in the same zircaloy cladding tubes .

ICP-AES法测定铀铌锆合金中的铌和锆

Determination of Nb and Zr in U-Nb-Zr Alloys by ICP-AES

用SEM波谱分析手段，定性研究了合金元素铌在新锆合金中的存在方式。

The existing form of niobium in zirconium-based alloy containing Fe , Sn , Cr alloying elements was researched qualitatively by means of SEM .

ICP-AES测定锆合金（Zr-2、Zr-4）中10种微量杂质元素

Determination of 10 Trace Impurity Elements in Zirconium Alloy by ICP-AES

在不含Cr的锆合金中添加合金元素Nb，不仅改善了焊接区的耐腐蚀性能，而且不会引起腐蚀时吸氢增加。

Adding Nb alloying element in zirconium alloys without Cr , not only improves the corrosion resistance , but also make hydrogen uptake not to increase .

对国产及法国产两种M5锆合金包壳管进行拉伸性能测试，包括轴向拉伸及其环向拉伸。

Axial and ring tensile test of M5 alloy cladding tube was carried out .

分析了核用锆合金爆破试验失败的原因，针对外径不大于10mm的管材和外径大于10mm管材爆破试验进行了改进，设计了2种规格的管材试样联接接头，改进了管材试样焊接的保护装置。

The reason of burst testing for zirconium alloy tube being defeated was analyzed .

M5锆合金高频感应氧化硬质陶瓷膜制备技术及其耐腐蚀性能研究

Research on Preparing Technology and Corrosion Resistance of Hard Ceramic Layer by High-Frequency Induction Oxidation on M5 Zirconium Alloy

M5锆合金主要应用于核反应堆堆芯的燃料包壳和结构件。

M5 zirconium alloy is mainly applied in the nuclear reactor core as the fuel cladding tubes and structure materials .

热处理制度对Zr-Sn-Nb新锆合金耐腐蚀性能的影响

Effect of Heat Treatment on the Corrosion Resistance for Zr-Sn-Nb New Zirconium Alloy

研究用电感耦合等离子体发射光谱法（ICP-AES）直接测定锆合金中常量及微量元素：Fe、Cr、Ni、Sn、Nb的分析方法。

The method for direct determination of major and trace elements including : Fe 、 Cr 、 Ni 、 Sn and Nb in zirconium alloys by ICP-AES was studied . The suitable analytical lines were selected .

变形及热处理对Zr-Sn-Nb新锆合金第二相粒子的影响

Effect of Deformation and Heat Treatment on the Second Phase Particulars of Zr-Sn-Nb New Zirconium Alloy

在活性氧流动介质和干空气中，用高频感应氧化工艺在M5锆合金表面生成氧化锆陶瓷膜进行了研究。

It is researched the preparation of ceramic layer on the surface of M5 zirconium alloy by high-frequency induction oxidation process in active flow oxygen medium and in dry air .

M5合金是一种适用于高燃耗组件的新型锆合金，主要用作燃料棒包壳、端塞、导向管和定位格架材料。

M5 alloy was a new zirconium alloy used in high burn up assembly such as fuel cladding , end plug , guide tube and grid spring and so on .

4用Ag做中间层阻隔了316L不锈钢中的Ni和Fe元素向锆合金的扩散，避免了脆性的Zr3Fe、NiZr2、Ni2Zr3等金属间化合物的生成；

By using Ag as intermediate layer , the diffusion of Ni and Fe from 316L stainless steel side to Zr-4 can be prevented and the formation of brittle intermetallic compounds like Zr_3Fe 、 NiZr_2 、 Ni_2Zr_3 can be avoided .

本文提出利用热处理工艺改善再结晶退火态M5锆合金的组织和性能，旨在提高核燃料包壳的寿命，为促进核燃料包壳国产化提供一定的理论参考和依据。

In order to extend the life of nuclear fuel cladding tubes , this paper proposes to improve microstructure and properties by heat treatment of M5 zirconium alloys on recrystallization annealing state .

所以，伙计们，如果你想在耳朵上戴一枚立方体的锆合金，因为你最喜欢的R&B歌手或rap明星也戴了一枚，你认为比较酷，你的潜在雇主可能不这样认为。

So guys , if you think that wearing a cubic zirconium on your ear because your favourite R & B artist or rap star wears one and you think that actually is kind of cool , that 's not necessarily how your potential employer is going to see it either .

主要研究结果如下：利用光学金相显微镜，透射电镜，扫描电镜等分析方法对再结晶退火态的M5锆合金进行组织结构研究。

The main research results are as follows : Using optical metallographic microscope , transmission electron microscopy , scanning electron microscopy and other analysis methods to research on microstructure of recrystallization annealing state of M5 zirconium alloys .

锆合金作为轻水核反应堆燃料元件的包壳材料已得到了广泛的应用并积累了丰富的经验，因而仍被列为SCWR潜在的应用材料。

As a light water nuclear reactor fuel cladding material , Zr alloy has been wide used and its application experience accumulated , hence it is the potential materials for SCWR .

描述了用单片试样法研究合金成分对Zr-Sn-Nb-Fe-Cr系锆合金在350℃，LiOH水溶液和400℃蒸汽中耐腐蚀性能影响的结果。

The effect of alloying composition on the corrosion resistance of zirconium alloys with Zr-Sn-Nb-Fe-Cr system tested in 350 ℃, LiOH solution and 400 ℃ steam was investigated using Single-Specimen-Method .

研究了Zr-Sn-Nb-Fe-Cr锆合金真空电子束焊接样品的拉伸和抗腐蚀性能，结果表明，焊接样品室温和375℃的拉伸性能略低于母材；

The mechanical properties and corrosion resistance of the sample made by vacuum electron bean welding of Zr-Sn-Nb-Fe-Cr zirconium alloy were investigated . The results show mechanical properties at room temperature and 375 ℃ temperature of welding sample were lower than matrix .

辐照对堆用锆合金腐蚀行为的影响原子核多重碎裂研究

Effects of irradiation in nuclear reactors on Corrosion Behavior of Zircaloys

热处理对锆合金钝化电流密度的影响

Effects of heat treatment on the passive current density of zircaloy-4

锆合金与不锈钢过渡管接头的爆炸焊接

Explosive Welding of Transition Pipes Joint With Zirconium Alloy stainless Steel

机械合金化制备纳米钛-锆合金的研究进展

Research Progress in Mechanical Alloying of Nano-Synthesizing of Ti and Zr

材料状态对锆合金碘致应力腐蚀的影响

Effects of Material Condition on Iodine Induced SCC Behavior of Zircaloy

新锆合金低周疲劳特性研究

Fatigue Characteristics of New Zirconium-Based Alloys Under Low Cycle Loading

设计了一种适用于锆合金棒的超声波自动检测系统。

An automatic ultrasonic testing system for zirconium alloy bars was designed .

块状非晶锆合金弹丸侵彻装甲性能研究

Study on armour-penetrating behavior of bulk amorphous Zr alloy bullet