Preliminary design of the suppressive containment system based on HPR1000

被引:36
|
作者
Qi, Xiangjie [1 ]
Yu, Fangxiaozhi [2 ]
Meng, Zhaoming [1 ]
Sun, Zhongning [1 ]
Zhang, Nan [1 ]
Guo, Zehua [1 ]
机构
[1] Harbin Engn Univ, Heilongjiang Prov Key Lab Nucl Power Syst & Equipm, Harbin 150001, Peoples R China
[2] China Nucl Power Engn Co Ltd, Beijing 100840, Peoples R China
关键词
STEAM CONDENSATION; COOLING SYSTEM; WATER REACTOR; HYDROGEN; CONVECTION;
D O I
10.1016/j.nucengdes.2023.112743
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
The current HPR1000 has a high construction cost and weak economic competitiveness due to its complex system and large containment. This study proposes a conceptual design of an advanced containment system based on HPR1000, which aims at reducing the construction cost of nuclear power plants without reducing suppressed by ACP instead of the traditional large-volume suppression concept. And due to the significant condensation of steam within the ACP water, the transportation of air into the ACP results in a reduction in the air mass fraction in the vicinity of the passive containment heat removal system (PCHR) located within the containment structure. This phenomenon subsequently leads to an enhancement in heat transfer performance. In addition, ACP also serves as the water source for the safety injection system, the reactor cavity water injection system, and the core replacement system. Compared with HPR1000, the system of the preliminary design has been greatly simplified, and the size of the containment vessel has been reduced by nearly 47%. The simulation of the large-break loss-of-coolant accident (LBLOCA) scenario has been conducted to examine the response of the containment system, specifically focusing on the performance of the safety injection system and suppression system. The results show that the integrity of the containment and core was ensured throughout the accident, and there was a safety margin.
引用
收藏
页数:8
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