核供热堆海水淡化系统的热工水力学特性  

Thermal hydraulic performance of seawater desalination system using a nuclear heating reactor

作　　者：吴少融[1] 杜小泽[1] 

机构地区：[1]清华大学核能技术设计研究院,北京100084

出　　处：《清华大学学报（自然科学版）》2002年第5期642-645,共4页Journal of Tsinghua University(Science and Technology)

摘　　要：针对与低温核供热堆相耦合的竖管多效蒸发海水淡化系统 ,建立了物理数学模型 ,探讨该系统的热工水力学特性。采用等温差和分段等面积两种温差分配方案对系统进行设计。分析了系统各效的蒸发器和预热器面积、平均换热系数以及淡水产量等随效数的变化规律。结果表明 ,经过适当的温差调整 ,两种方案下产水比都可以达到 2 0以上 ,但等面积温差分配设计方案在系统的建设上将更具优势。A physical-mathematical model was developed to explore the thermal hydraulic performance of a vertical tube multi-effect distillation seawater desalination system coupled with the nuclear heating reactor. Two temperature difference distribution schemes, equal temperature difference and equal heat transfer area temperature difference, were used for the system design. The results indicate that the gain-output-ratio with both temperature difference distribution schemes can be up to 20. However, the design with the equal heat transfer area temperature difference is more suitable for a tower design. The results would be helpful for designing a large capacity vertical tube multi-effect distillation desalination plant.

关 键 词：核供热堆 海水淡化系统 热工水力学特性 多效蒸发 蒸发器 预热器 换热系数 

分 类 号：P747.15[天文地球—海洋科学] TL33[核科学技术—核技术及应用]