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Study on characterization of ceramic materials for nuclear engineering

核工程陶瓷材料表征研究

基本信息

批准号：
61470161
负责人：
TAKAHASHI Yoichi
金额：
$ 3.07万
依托单位：
University of Tokyo
依托单位国家：
日本
项目类别：
Grant-in-Aid for General Scientific Research (B)
财政年份：
1986
资助国家：
日本
起止时间：
1986 至 1987
项目状态：
已结题

项目摘要

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.

陶瓷材料在核工程中占有重要地位。它们具有如此复杂的结构，气体通过它们的传输过程是不容易理解的。本研究的目的是测量聚变堆包层材料的结构、吸附特性和气体渗透特性，以阐明它们之间的关系。烧结氟化锂（LiF）的透气性和孔结构作为一种透气性气体与烧结基体之间相互作用较弱的体系，选用LiF和Ar-He混合气体，在不同的烧结条件下制备了LiF样品，并对其透气性和扩散性进行了研究。结果表明，它们可以表示为一个简单的函数的孔隙率在基质中测定的压汞仪。H_2O在Li_2 O-LiOH混合体系中的吸附及平衡蒸气压测定了H_2O在不同表观粒径的Li_2O样品上的吸附量及吸附焓变，研究了渗透气体与烧结基体的化学作用。此外，在350-620 ℃的温度范围内，高精度地得到了Li_2 O-LiOH混合物体系中H_2O的平衡蒸气压.聚变堆包层中氚存量的估算为了估算RFP型聚变堆包层中的氚存量，编制了计算包层中氚输运的计算程序。在本规范中，充分利用了本研究中获得的一些数据，并对这些数据的可用性和重要性给予了肯定，最终报告已发表。