聚变堆强磁场与高核热梯度下包层液态铅锂载氚热磁流体MHD流动氚传输机理研究

The liquid metal lead lithium blanket is a major candidate blanket for the design of fusion reactor and the future demonstration reactor, which has high tritium breeding ratio, strong heat-carrying ability, high heat transfer effect, relatively simple structure,and easy real-time online extracting tritium. However, the tritium transport mechanism of thermal magnetic fluid MHD flow of liquid lead lithium carrying tritium in the condition of a strong fusion magnetic field and high power density nuclear heat, is the most challenging key issues for the development of this type of blanket, and is also the basis of the tritium fuel cycle and the tritium safety of the fusion reactor. The simulation experiment system for the blanket thermal magnetic fluid and tritium transfer, and a boundary layer measurement technique, will be established for this project. It is according to the theory of electromagnetic coupling, considering the exchange of momentum and energy of gas liquid two-phase, and couples tritium transfer equations for numerical simulation. The dynamic behavior of the thermal magnetic fluid MHD caused by the gradient of nuclear thermal buoyancy will be researched. The physical processes that appear in the liquid lead lithium velocity boundary layer, thermal boundary layer, and tritium concentration boundary layer in the condition of a strong magnetic field and a gradient of nuclear thermal will be explored. The influence on tritium infiltration caused by the velocity of liquid lead lithium, the tritium infiltration ratio in silicon carbide flow channel insert (FCI) and alumina coat will be investigated. Heat and mass transfer model of liquid lead lithium thermal magnetic fluid MHD flow will be established. Mass transfer coefficient will be acquired and the effect on flow and heat and mass transfer by FCI infiltration will be probed. Thus, it can establish a basis for the application of liquid metal blanket carrying tritium thermal magnetic fluid heat and mass transfer.

液态金属铅锂包层氚增殖率高、载热能力强、热转换效率高、结构简单、实时在线提氚，是聚变堆设计和未来示范堆主要候选包层，但聚变强磁场和高核热梯度下液态铅锂载氚热磁流体气液两相MHD流动氚传输与渗透机理是该型包层发展最具挑战的关键问题，也是聚变堆氚燃料循环和氚安全的基础。本项目依据电磁耦合理论，考虑气液两相的动量交换和能量交换，耦合氚传输方程进行数值模拟，结合研发的包层热磁流体氚传输模拟实验系统和UDV测量边界层技术，探索强磁场与高核热梯度浮力下的载氚热磁流体MHD动力学行为和速度边界层、热边界层与氚浓度边界层中出现的物理过程，探讨液态铅锂流速、碳化硅插件(FCI)及其氧化铝涂层对氚渗透的影响因素，建立铅锂载氚热磁流体MHD流动传热传质模型，获取传质系数，并分析FCI浸润性对流动与传热传质的影响，为液态金属包层载氚热磁流体流动传热传质的应用建立基础。

液态金属铅锂包层氚增殖率高、载热能力强、热转换效率高、结构简单、实时在线提氚，是聚变堆设计和未来示范堆主要候选包层，但聚变强磁场和高核热梯度下液态铅锂载氚热磁流体气液两相MHD流动氚传输渗透机理与提取以及第一壁的高效冷却技术，是该型包层发展最具挑战的关键问题。. 本项目共发表收录论文24篇，其中SCI论文21篇(I区6篇)，EI论文1篇，核心期刊论文2篇。搭建实验系统三套，申请国家发明专利2项，培养博士研究生2名。主要研究内容和重要结果为：(1) 考虑液态金属和分子态氚的气液两相动量交换和能量交换，耦合氚传输方程发展了三维数值模拟方法和程序并进行数值计算，获得了强磁场与高核热梯度浮力下的载氚热磁流体MHD动力学行为和氚渗透的影响规律，给出了传热传质模型和传热传质系数；(2) 研发了包层热磁流体高真空浸润性、高真空动密封旋转式高温液态金属腐蚀、旋转叶片纳米流体腐蚀等装置，实验获得了液态包层中铅锂环境对结构材料、碳化硅插件(FCI)和涂层的腐蚀规律和浸润性特性，给出了不同温和流速下纳米流体对包层结构和功能材料的腐蚀特性；(3) 研制了液态包层多流场藕合传热、纳米流体超汽化强化传热实验系统，发展了UDV边界层测量和激光诱导荧光测量技术，实验测量了高热流条件下氦气、压力水、氦与二氧化碳混合气体、纳米流体等不同工质冷却包层第一壁时的强化换热特性，并进行了三维数值验证，为第一壁的高效冷却提供了可行的工程方案；(4) 开展了氚增殖材料钛酸锂粉体和钛酸锂小球的制备与性能表征研究，为相关聚变研究单位提供了批量级增殖材料用于释氚实验和热工特性实验；(5) 发明了一种用于聚变堆液态金属包层在线提氚的真空雾化螺旋喷嘴装置及方法，提氚效率也可达到90%以上，可有效解决聚变堆液态金属包层高效在线提氚的难题。项目研究成果为液态金属包层载氚热磁流体流动传热传质特性、在线提氚和第一壁的高效冷却建立了应用基础。