Thermal hydraulic analysis of loss of flow accident in the JRR-3M research reactor under the flow blockage transient

被引：7

作者：

Guo, Yuchuan ^{[1
]}

Wang, Guanbo ^{[1
]}

Qian, Dazhi ^{[1
]}

Yu, Heng ^{[1
]}

Hu, Bo ^{[1
]}

Guo, Simao ^{[1
]}

Mi, Xiangmiao ^{[1
]}

机构：

[1] China Acad Engn Phys, Inst Nucl Phys & Chem, Mianyang 621900, Peoples R China

来源：

ANNALS OF NUCLEAR ENERGY | 2018年 / 118卷

基金：

中国国家自然科学基金;

关键词：

Flow blockage; LOFA; Natural circulation; CORE; CHANNEL; FUEL;

D O I：

10.1016/j.anucene.2018.04.014

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 transient thermal-hydraulic behavior of loss of flow accident (LOFA) in the JRR-3M 20MW pool-type research reactor under flow blockage is investigated using RELAP5/MOD3.4 code. The core is divided into 7 hot channels, 1 average channel and 1 bypass channel to take into account the interaction between the blocked channel and adjacent channels. Blockage ratios considered in the work includes 0%, 40%, 50%, 60%, 70%, 80% and 100%. MDNBR and fuel central temperature are investigated to estimate the integrity of the fuel plate. Compared with the accident consequence of flow blockage, the results indicate that it is more likely for LOFA under flow blockage to occur departure from nucleate boiling (DNB) in the same blockage ratio. Even when the flow channel is totally blocked, the fuel temperature is still within the safety limit, which is set as 400 degrees C. And the emergency shutdown of the main loop low-flow signal can effectively mitigate the accident consequences. The reactor core is ultimately in a safe quasi-steady state when the natural circulation is completely established. (C) 2018 Elsevier Ltd. All rights reserved.

引用

页码：147 / 153

页数：7

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