Study on characterization of ceramic materials for nuclear engineering

陶瓷材料在核工程中非常重要。他们有这样一个复杂的文本，即通过天然气运输过程是不容易理解的。本研究的目标是衡量结构和吸收的特征以及在顺序中确定聚变反应器空白材料之间的关系。本研究是在以下主题中进行的：1。气体的渗透性和晶体管（LiF）的孔隙结构;作为一个系统在渗透性气体和渗透性矩阵之间存在较弱的相互作用，一对LiF和Ar-He气体混合物被选择，以及气体渗透性和通过LiF样本在各种互连条件下准备的差异。这是显而易见的，因为它们可以被一个汞污染物测定器所揭示的基质中的一个简单功能。H_2O on Li_2O and equilibrium vapor pressure of H_2O in the system of Li_2O-LiOH mixture。Adsorption amount of H_2O on lithium oxide （Li_2O） samples with various sizes of apparent particle radius as well as its enthalpy change was measured to investigate the chemical interaction of permeating gas and sintered matrix。此外，在该系统中的H_2O-LiOH混合物中，H_2O的等效蒸汽压力在350-620 ° C的宽温度范围内达到了高准确性。在fusion reactor blanket中建立一个tritium inventory。在fusion reactor中建立一个tritium inventory of RFP-type fusion reactor。在此代码中，在此研究中发现了一些数据，并且其可用性和重要性已被识别。关于此项目已发表的最终报告。

Ceramic materials are very important in nuclear engineering. They have such complicated textures that gas transport process through them is not easy to understand. The aim of this study was to measure the structure and the characterisitics of adsorption and the gas permeation in order to clarify the relationship among them on fusion reacter blanket materials.This study was performed in the following themes:1. Gas permeability and pore structure of sintered lithium fluoride(LiF).As a system having weak interaction between permeating gas and sintered matrix, a pair of LiF and Ar-He gas mixture was chosen, and the gas permeability and the diffusity through LiF samples prepared in various sintering condition. It was shown that they can be expressed by a simple function of porosity in the matrix determined by a mercury porosimeter.2. Adsorption of H_2O on Li_2O and equilibrium vapor pressure of H_2O in the system of Li_2O-LiOH mixture.Adsorption amount of H_2O on lithium oxide (Li_2O) samples with various sizes of apparent particle radius as well as its enthalpy change was measured to investigate the chemical interaction of permeating gas and sintered matrix. In addition, equilibrium vapor pressure of H_2O in the system of Li_2O-LiOH mixture was obtained in high accuracy in the wide temperature range of 350-620゜c.3. Estimation of tritium inventory in fusion reactor blanket.Computational code to calculate tritium transport in fusion reactor blanket was constructed in order to estimate the tritium inventory of RFP- type fusion reactor. In this code, some data obtained in this study swre utilized, and its availability and importance were recognized.The final report on this project has been published.