Numerical investigation on the CHF model and prediction for the external cooling channel of lower head

被引:0
|
作者
Li Dan [1 ]
Peng Changhong [1 ]
Li Songwei [2 ]
Guo Yun [1 ]
机构
[1] Univ Sci & Technol China, Sch Phys Sci, Hefei 230026, Anhui, Peoples R China
[2] Nucl Power Inst China, State Key Lab Reactor Syst Design Technol, Chengdu 610041, Peoples R China
关键词
Critical heat flux; Bubble nucleation density; Lower head; NUCLEATION SITE DENSITY; CFD; NEPTUNE;
D O I
10.1016/j.anucene.2019.02.036
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
External cooling of the lower head can reduce the possibility of the damage to the pressure vessel in serious accidents. However, when the core melt heats the lower head with a high heat flux subcooled boiling under natural circulation may cause bubble accumulation, which results in the deterioration of heat transfer or even radioactive leakage. This phenomenon is essentially the critical heat flux (CHF) on a curved surface with a downward heating boundary. The estimation of this phenomenon is indispensable for reactor safety design. In this paper, improvement in the nucleation density model exhibits higher resulting calculation performance for CHF with new geometries or working conditions. The CHF values and CHF distribution along the ellipsoidal and spherical structures are obtained, and detailed comparison between these two structures is made. The characteristics of elliptical cooling channel prove completely different from those of spherical structure, which requires more experimental studies. (C) 2019 Elsevier Ltd. All rights reserved.
引用
收藏
页码:232 / 239
页数:8
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