氢化锆

氢化锆中氢的散射律和散射矩阵研究

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

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。

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

氢化锆表面CO2反应层结构分析

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

时间对CO2反应法在氢化锆表面生成氧化膜影响分析

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

氢化锆表面Cr-C-O氢渗透阻挡层XPS分析

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

氢化锆中氢的散射矩阵的计算和WIMS库的扩充及评价

Calculation of Scattering Matrix of H in ZrH and Evaluation of WIMS Library Data

Zr-2合金中应力及应变诱发氢化锆析出过程的电子显微镜原位研究

In situ electron microscopy study on precipitation of zirconium hydrides induced by strain and stress in Zircaloy-2

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。

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 .

氢化锆表面电镀铬制备氢渗透阻挡层的研究

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

氢化锆慢化反应堆系统含锆甲醇催化剂的比表面与催化活性

Catalytic activity and BET surface area of methanol synthetic catalyst containing zirconium

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

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

含锆燃料的无水氢氯化氢化锆空间动力反应堆镍氢蓄电池材料用氧化锆布膜中铝含量的分析测试技术

Analytical Testing of Aluminum Content in Zirconium Oxide Cloth Film in Hydrogen-Nickel Battery

氢化锆固态零功率反应堆及其应用研究

Zirconium-hydride solid zero power reactor and Its Application Research

螺旋线行波管慢波系统的综合热分析法氢化锆慢化反应堆系统

Synthetic Analysis Method of the Heat Dissipation Capability of Slow-Wave Structure for Helix TWT

氢化锆高温抗氢渗透涂层研究

Study on Hydrogen Permeation Barrier of Zirconium Hydride

二氢化锆及其同位素生成热力学函数的理论计算

Thermodynamic theoretical calculation of zirconium hydrides Theoretical study

氢化锆慢化反应堆系统基于硼氢化钠制氢燃料电池供氢系统设计

Design of hydrogen generation systems for fuel cells by using hydrolysis of sodium borohydride

氢化锆慢化介质中的热中子能谱

Thermal neutron spectrum of zirconium hydride moderator

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。

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

用核噪声方法测量氢化锆零功率堆的瞬发中子衰减常数

Prompt neutron decay constant measurement on zrh_ ( 1.7 ) zero power reactor from nuclear noise analysis

氢化锆和钒的散射核

Scattering kernel for zrh_2and V

堆燃料元件锆包壳形成氢化锆的研究概况

General situation of the research work on zirconium hydrides formed in zirconium cladding of nuclear fuel assembles

因此必须使氢化锆结构材料具有尽可能低的氢渗透率。

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

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 was manufactured by electrodeposited chromium on zirconium hydride and the anti-permeation effect of the Cr coatings were 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。

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

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。

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 .