基于过冷沸腾的中性束注入系统高热流部件强化传热特性研究

The neutral beam injection (NBI) with high power which is one of the effective means of auxiliary heating and temperature maintain, has been a research hotspot in the field of controlled nuclear fusion. When the NBI system operate on high current and high power mode, the components inside the system will suffer particle bombardment of long pulse and high power，which will restrain the heat transfer caused thermal stress damage. The damage has been the main and key problem of the development of the NBI system for the fusion reactor..In order to solve the upper problems, through theoretical analysis, numerical simulation and the experimental study, the non-uniform beam energy distribution caused by neutral particle transformation and injection and the flow field-heat transfer- thermal stress coupling effect of the high heat flux components generated by the repeated long pulse loading of beam particle in the MW level NBI system, will be studied. The influence mechanism on the heat transfer and structure thermal stress of the key parameters of heat transfer enhancement technology based on subcooled boiling will be analyzed. The high-heat-component samples with the enhanced heat transfer structure of MW level NBI system is firstly designed and realized, and their experiments of heat transfer performance testing and the thermal stress limit testing are also implemented. According to the experimental results, as the prediction criteria of the safe operation of the system, the critical heat flux empirical criterion and thermal fatigue life prediction model of the test sample under the repeated loading of the long-pulse beam will be derived. This project has very important theoretical and practical value for the independent design of the heat transfer strengthen components in the fusion reactor.

中性束注入（NBI）加热是等离子体辅助加热和维持的有效手段，是受控核聚变领域的研究热点。NBI系统强流、准稳态、高功率运行时内部高热流部件反复遭受长脉冲强流粒子流轰击，由此引发的部件换热能力差、热应力损伤等问题已成为限制系统发展的瓶颈，也是目前国内外面向聚变堆的NBI系统建设中急需解决的难题。.针对上述问题，本项目通过理论、仿真和实验手段深入研究面向聚变堆的MW级NBI系统中性粒子转化和注入过程引发的非均匀束能分布，分析反复长脉冲加载对高热流部件产生的流场-传热-热应力耦合效应，探索过冷沸腾强化换热技术关键参数对传热和热应力的影响。项目首次设计实现MW级NBI系统高热流部件强化换热结构样品及其换热性能与热应力极限测试实验，研究部件在反复热负荷作用下的临界热流值等经验准则和热疲劳寿命预测模型，为系统安全运行提供预测判据。项目研究对我国聚变堆强化换热装置的自主设计具有重要的理论和工程价值。

中性束注入（NBI）加热是等离子体辅助加热和维持的有效手段，是受控核聚变领域的研究热点。NBI系统强流、准稳态、高功率运行时内部高热流部件反复遭受长脉冲强流粒子流轰击，由此引发的部件换热能力差、热应力损伤等问题已成为限制系统发展的瓶颈，也是目前国内外面向聚变堆的NBI系统建设中急需解决的难题。.针对上述问题，本项目通过理论、仿真和实验手段深入研究面向聚变堆的MW级NBI系统中性粒子转化和注入过程引发的非均匀束能分布，建立了适用于NBI系统高热流部件过冷沸腾瞬态汽液相变模型，分析反复长脉冲加载对高热流部件产生的流场-传热-热应力耦合效应，探索过冷沸腾强化换热技术关键参数对传热和热应力的影响。并依托搭建的高热流测试实验台开展了MW级NBI系统高热流部件强化换热结构样品及其换热性能与热应力极限测试实验，完成了样品热疲劳应力的探索，为系统安全运行提供了预测判据。为面向未来聚变堆的高热流装置的自主设计提供了新思路。