The suppression pool technology is the key to achieve the miniaturization of containment in floating nuclear power plant, of which immerged steam and non-condensable gas mixture jet direct contact condensation is the predominant technology. In the present study, theoretic analysis, CFD simulation and experimental validation were introduced to study the steam plume dynamics and the heat transfer between the phase interface, of which sensitivity analysis were also developed about the correlative factor. Functional correlation related to heat transfer, such as the structure and shape of the jet, immergence level, the mass flux and proportion of the steam and non-condensable gas, the temperature of the water were investigated, so as the influence of the non-condensable gas to the heat transfer. As a result, an approach to enhance the heat transfer from immerged steam and non-condensable gas mixture jet direct contact condensation were explored, which will provide a science criterion to the optimal design and miniaturization of the system.
抑压水池技术是实现浮动核电站安全壳小型化的关键技术途径,其核心技术在于蒸汽-不凝性气体混合浸没射流直接接触冷凝。本项目以蒸汽-不凝性气体混合浸没射流直接接触冷凝传热机理为研究目标,重点关注影响直接接触冷凝的汽羽动力学及相界面传热等相关因素,采用理论分析、CFD模拟及实验验证方法,针对影响直接接触冷凝的汽羽行为、相界面特性等相关因素开展敏感性分析,明确喷嘴结构形状、浸没深度、蒸汽-不凝性气体混合物配比及质量流量、水池过冷度等参数与直接接触冷凝传热特性之间的函数关系,揭示不凝性气体对蒸汽浸没射流直接接触冷凝的影响规律及影响程度,探索强化蒸汽-不凝性气体混合浸没射流直接接触冷凝传热的途径,为优化系统设计、实现系统小型化提供科学判据。
抑压水池技术是实现浮动核电站安全壳小型化的关键技术途径,其核心技术在于蒸汽-不凝性气体混合浸没射流直接接触冷凝。本项目以蒸汽-不凝性气体混合浸没射流直接接触冷凝传热机理为研究目标,重点关注影响直接接触冷凝的汽羽动力学及相界面传热等相关因素,采用理论分析、CFD模拟及实验验证方法,针对影响直接接触冷凝的汽羽行为、相界面特性等相关因素开展敏感性分析,明确喷嘴结构形状、浸没深度、蒸汽-不凝性气体混合物配比及质量流量、水池过冷度等参数与直接接触冷凝传热特性之间的函数关系,揭示不凝性气体对蒸汽浸没射流直接接触冷凝的影响规律及影响程度,探索强化蒸汽-不凝性气体混合浸没射流直接接触冷凝传热的途径,为优化系统设计、实现系统小型化提供科学判据。
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数据更新时间:2023-05-31
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