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包壳

na.cladding; envelope; involucrum
网络jacket; can; jacketing

包壳

英-汉网络释义

包壳

cladding

核电专业英语词汇 - 豆丁网 ... civil service 行政事务 cladding 包壳 abnormal condition 异常工况 ...

jacket

核能专业词汇英语翻译(F-L) ... j j coupling j j 耦合 jacket 包壳 jacketed counter 带壳计数管 ...

involucrum

...其与存活的骨分开，形成死骨片，骨膜反应生成新骨称为包壳(involucrum)，包裹感染骨和坏死骨，以后包壳出现缺损形成骨 …

can

核能专业词汇英语翻译(C) -亿城英语 ... campaign 炉龄期 can 包壳 can material 包壳材料 ...

jacketing

核能专业词汇英语翻译(F-L) ... jacketed counter 带壳计数管 jacketing 包壳 jaw 钳口 ...

Enclosure

材料科学专业英语词汇_专业词汇_专业英语... ... Encapsulation 封装 Enclosure 夹杂物，包壳 encoustic tile 彩纹瓦 ...

back shell

汽车术语-中英对照-企业博客网(bokee.net) ... 底壳 base assembly 包壳 back shell 底架 inolucrum ...

sheath

核能专业词汇英语翻译(R-Z) ... shearing test 剪切试验 sheath 包壳 sheathed pump 密封泵 ...

例句：

The outer part of the envelope now has the form of a thick shell or dust cocoon .

现在包壳的外层部分是厚壳层或尘埃包层的形状。

The embryo inside the protostar is less massive than the envelope ; most of the mass is still falling inward .

原恒星内部的胚胎的质量比包壳小，大部分物质一直在朝中心落去。

Conclusion : The X-ray character of giant cell tumor of bone is at the soap bubbles shadow and the b. . .

结论：皂泡影及骨包壳是骨巨细胞瘤的 X 线特征。

Temperature and humidity effects on the corrosion of aluminium-base reactor fuel cladding materials during dry storage .

温度和湿度对干贮存铝基反应堆燃料包壳腐蚀的影响 …[中国核科技信息与经济研究院 ]。

The metal matrix dispersion fuel rod consists of the metal cladding and the dispersion nuclear fuel meat.

棒状弥散型燃料由弥散型燃料芯体和包壳构成。

The expansion of the envelope will gradually thin out the obscuring dust.

包壳的膨胀会使不透明的尘埃逐渐变得稀

Are trapped within the fuel pellets and claddings .

产生的物质都密封在燃料芯块和包壳内。

So that is the actual skin envelope here as well. -Yeah .

所以这里也是实际的皮肤包壳。-是的。

Simulation of a pellet -clad mechanical interaction with ABAQUS and its verification

模拟芯块 -包壳机械相互作用及其验证

encasing steelwork for fire protection; encased steelwork for fireproofing

钢结构防火包壳

A Strain-based Clad Failure Criterion for Reactivity Initiated Accidents in Light Water Reactors

轻水堆反应性引发事故基于应变的包壳损伤判据

Iodine Induced Stress Corrosion of New Zirconium Alloy Cladding

新锆合金包壳的碘致应力腐蚀研究

Progress in Research on Iodine-induced Stress Corrosion Crack of Zirconium Cladding

锆合金包壳的碘致应力腐蚀研究进展

A safety check-up method for decommissioned reactor fuel element cladding

一种用于退役核燃料元件包壳的破裂检测技术

Corrosion of spent nuclear fuel aluminium cladding in ordinary water

在普通水中乏核燃料的铝包壳的腐蚀

Minimum cladding thickness of material test reactor fuel plates

材料试验堆燃料板的最小包壳厚度

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

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