Hydrogen permeation barrier was manufactured by electrodeposited chromium on zirconium hydride and the anti-permeation effect of the Cr coatings were investigated .

采用电镀铬 法在 氢化 锆 表面制备了氢渗透阻挡层，分析了电镀工艺参数对镀层生长的影响，并对镀层的阻氢效果进行检测。

Hydrogen permeation barrier can be prepared on the surface of zirconium hydride when zirconium hydride reacts with CO_2 and phosphorous red . The cross-sectional morphology and phase structure of the zirconium dioxide film are observed and investigated by the techniques of XPS SEM and XRD .

利用 ZrH2和CO2、P反应在氢化 锆表面制备氢渗透阻挡层，并借助SEM、XPS和XRD对膜层进行截面形貌观察和物相分析。

Feasibility Analysis for Application of Compact Power Reactor Fuelled with Uranium Zirconium Hydride

铀 氢化 锆 元件小型动力堆应用可行性分析辐照二氧化铀燃料 元件 氢化 锆 慢 化反应堆系统

The Zirconium Hydride Solid Zero Power Reactor built at China Institute of Atomic Energy is introduced .

介绍了建于中国原子能科学研究院的 氢化 锆固态零功率反应堆。

Influence of Time upon Oxide Film on the Surface of the Zirconium - Hydride by the Method of CO2 Reaction

时间对CO2反应法在 氢化 锆表面生成氧化膜影响分析

Analysis of Cr-C-O Hydrogen Permeation Barrier on the Surface of the Zirconium Hydride by XPS

氢化 锆表面Cr-C-O氢渗透阻挡层XPS分析

Analysis of Pulse Parameters for Uranium Zirconium Hydride Reactor

铀 氢 锆反应堆脉冲参数分析

Thermal neutron spectrum of zirconium hydride moderator

氢化 锆慢化介质中的热中子能谱

Moderators work at temperature between 650 ℃ and 750 ℃ in space piles in this case zirconium hydride ( atom ratio of H / Zr > 1.8 ) loses its hydrogen easily .

在空间堆中，慢化剂的工作温度范围为650～750℃，而在此温度下， HZr原子比大于1.8的 氢化锆中的氢很容易析出。

Study on Hydrogen Permeation Barrier of Zirconium Hydride

氢化 锆 高温 抗氢渗透涂层研究

Desulfurization reactions of zirconium hydride reagents with organic compounds containing sulfur

锆 氢试剂与含硫有机化合物脱硫反应的研究

Zirconium hydride has excellent practical prospects due to its properties as neutron-moderator material in nuclear reaction piles .

氢化 锆因具备诸多作为反应堆中子慢化材料的优点，有着良好的应用前景。

The first pulsed reactor in our country is a small pool type research reactor using a solid homogeneous mixture of enriched uranium and zirconium hydride rod as its fuel-moderator elements .

我国第一座脉冲反应堆是座小型池式研究堆，采用铀 氢 锆（UZrH（1.6））燃料-慢化剂粗棒元件。

Study of nuclear safety parameters of uranium zirconium hydride pulsed research reactor core

铀 氢 锆脉冲堆堆芯核安全参数的计算

Therefore something must be done about zirconium hydride to prevent hydrogen from dispersing from its inner part .

因此必须使 氢化 锆 结构 材料具有尽可能 低的氢渗透率。

The technology to prepare hydrogen permeation barrier with electrodeposited chromium on zirconium hydride ( ratio of H and Zr is 1.801 ) was investigated .

研究了在 氢化 锆（H/Zr原子比为l.801）表面通过电镀铬制备氢渗透阻挡层的工艺。

Preparation of Hydrogen Permeation Barrier of Chromium Coating Electrodeposited on Zirconium Hydride

氢化 锆表面电镀铬制备氢渗透阻挡层的研究

Study on the scattering law and scattering kernel of hydrogen in zirconium hydride

氢化 锆中氢的散射律和散射矩阵研究

Generation of a Group Constants Library for Uranium Zirconium Hydride Reactor and Some Calculations of Core and Safety Parameters

铀 氢 锆堆群常数库的生成及堆芯的物理和安全参数的计算

Structure Analysis of Film Formed by Reaction of CO_2 and Zirconium Hydride

氢化 锆表面CO2反应层结构分析