zircaloy
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英汉解释
英英解释
例句
The Zircaloy casing is the second barrier to release that separates the radioactive fuel from the rest of the reactor.
锆锡合金形成第二道防护，把放射燃料跟反应堆其他的组成分隔开。
The Zircaloy casing is the first containment. It separates the radioactive fuel from the rest of the world.
这些锆锡合金密封罐子是首要的容器，把放射燃料跟其他事物隔开。
Measurement of hydriding susceptibility of zircaloy cladding by the tube-burst technique at high pressure and high temperature.
通过高压和高温下管破损测量锆合金包壳氢化敏感性…[中国核科技信息与经济研究院]。
The nuclear material itself was still intact, but the surrounding Zircaloy shell had started failing.
核材料自身还完好无缺，但是它们周围的锆锡合金已经熔化。
Differences in reactivity of oxide growth during the oxidation of Zircaloy-4 in water vapour before and after the kinetic transition.
在动力学转变之前和之后锆合金-4在水蒸汽中氧化作用期间氧化物生长反应性的差别…[中国核科技信息与经济研究院]。
In this paper, research results and disadvantages of main bonding process of zircaloy and stainless steel are reviewed.
分析了核反应堆用锆合金与不锈钢主要连接技术的研究结果及存在的问题。
Hardness and microstructural studies of electron beam welded joints of Zircaloy-4 and stainless steel.
锆-4合金和不锈钢电子束焊接点的硬度和微结构研究…[中国核科技信息与经济研究院]。
Influences of laser surface alloying with niobium (Nb) on the corrosion resistance of Zircaloy-4.
用铌进行激光表面合金化对锆合金-4抗腐蚀的影响…[中国核科技信息与经济研究院]。
"Fuel failure" is a better term to describe the failure of the fuel rod barrier (Zircaloy).
“燃料失效”是个更贴切的词汇来描述燃料棒这层屏障的失效（锆锡合金）。
And we'll also be putting the fuel pins in the same zircaloy cladding tubes.
我们也放入了燃料大头针，在同样的锆合金的管子里。
This is when the first containment, the Zircaloy tube, would fail.
而这样就会导致第一层护罩，燃料棒的锆锡合金外壳融化。
Determination of trace elements in steel, nickel-base alloy and zircaloy using time of flight inductively coupled plasma mass spectrometry
飞行时间-电感耦合等离子体质谱法测定钢、镍基合金及锆锡合金中痕量元素
Study of Hydrogen Absorption in Lithium Hydroxide Water Solution for Zircaloy Tubes
锆合金管材在氢氧化锂溶液中的吸氢研究
Discussion on Corrosion Transition Mechanism of Zircaloy
锆锡合金腐蚀转折机理的讨论
Determination of trace elements in steel, nickel base alloy and zircaloy using ICP-TOFMS
法测定钢、镍基合金及锆合金中痕量元素
Phase Transition Temperature of the New Zircaloy
新锆合金的相变温度
Research on Nodular Corrosion Resistance Performance of Zircaloy-4 Cladding Tubes
锆-4合金包壳管抗疖状腐蚀性能研究
Development of Research on Protective Zircaloy Cladding in Nuclear Reactor
核反应堆中防护包壳的研究进展
Research Development of Surface Modification of Zircaloy
锆合金表面改性研究进展
Microstructure Evolution of Oxide Films Formed on Zircaloy-4 during Autoclave Tests
锆-4合金在高压釜中腐蚀时氧化膜显微组织的演化
Effect of molybdenum ion implantation on corrosion resistance of zircaloy-4
钼离子注入对锆-4合金耐腐蚀性的影响
Bonding Process of Zircaloy and Stainless Steel
锆合金与不锈钢的连接技术
Progress in Study on Zircaloy Oxide Film
锆合金氧化膜研究进展
The Cracking Induced by Oxidation-Hydriding in Welding Joints of Zircaloy-4 Plates
氧化-氢化引起锆4板焊接接头的开裂
