安全壳非能动冷却能力分析计算  

Analysis and Calculation of Containment Passive Cooling Ability

作　　者：高剑峰 叶成[2] 

机构地区：[1]中广核工程有限公司,广东深圳518057 [2]上海核工程研究设计院,上海200233

出　　处：《原子能科学技术》2014年第12期2274-2279,共6页Atomic Energy Science and Technology

摘　　要：本文对LOCA工况长期稳定阶段安全壳非能动冷却系统的冷却能力进行分析计算。研究了安全壳外壁面与空气折流板之间内环廊的特性与参数。在假设安全壳内壁面温度的前提下,分析计算涉及的各传热过程,相关的安全壳外壁面冷却水膜蒸发量与未蒸发水温选用特定值。通过安全壳外壁面向内环廊空气散热量的两个相关等式形成闭环,进而修正假设的安全壳内壁面温度并重新迭代计算。计算结果表明,安全壳冷却导出热量为6.99 MW,而相应阶段安全壳内事故释放热量为6 MW,即对应本文分析的具体情况,安全壳非能动冷却设计是有效的。The cooling ability of containment passive cooling system was calculated for post LOCA long term steady phase.The critical parameters and inner annulus features between containment outer surface and air baffle were studied.With a containment inner surface temperature hypothesis value,each heat transfer mechanism related to containment passive cooling process was analyzed,while the vaporized water mass and the water temperature on containment outer surface without vaporization were given.Since containment outer surface transferring heat to inner annulus air bonded two equations,close iteration calculation loop was formed,and by further adjusting original temperature hypothesis value,the iterative calculation was repeated again.The results show that the containment passive cooling capability is equal to 6.99 MW,while the post accident released energy is 6MW at the corresponding accident phase,namely,for this concrete situation,thus the containment passive cooling design is effective.

关 键 词：非能动 安全壳冷却 迭代 WGOTHIC 

分 类 号：TL364.3[核科学技术—核技术及应用]