| 回流流动极限实验研究综述 |
| |
| 引用本文： | 彭云康. 回流流动极限实验研究综述[J]. 核动力工程, 1993, 14(6): 556-560 |
| |
| 作者姓名： | 彭云康 |
| |
| 作者单位： | 中国核动力研究设计院 成都，610005 |
| |
| 摘 要： | 回流冷凝是压水堆发生失水事故（ＬＯＣＡ）时的重要传热方式之一。当堆芯冷却剂严重丧失，自然循环又不能建立起来时，堆芯剩余释热依然能靠回冷凝带山。但在一定条件下会出现回流流动极限ＣＣＦＬ，并因此增加堆芯踝露程度。本文介绍了国外一些研究者在ＣＣＦＬ方面的研究成果，并建议开展ＣＣＦＬ研究。
|
| 关 键 词： | 回流流动极限 压水型堆 冷却剂丧失 |
A Summarization of Countercurrent Flow Limitation Experiment Stuidies |
| |
| Peng Yunkang. A Summarization of Countercurrent Flow Limitation Experiment Stuidies[J]. Nuclear Power Engineering, 1993, 14(6): 556-560 |
| |
| Authors: | Peng Yunkang |
| |
| Abstract: | Counterflow condensation is one of the important core cooling mechanisms during a loss of coolant accident (LOCA) of PWR. The core decay heat still can be removed, even for natural circulation can not be established where the reactor coolant inventory has been lost so significant, by counterflow condensation. However, there is a possibility that, for large core steaming rate, liquid holdup will occurred in some place, this situation is socalled countercurrent flow limitation (CCFL). A summarization of CCFL experiment study was summarized in this papaer, also some suggestions were propsed. |
| |
| Keywords: | PWR SBLOCA Counteraurrent Flow Limitation Steam generator Invert U tube Two-phase flow |
| 本文献已被 CNKI 维普 等数据库收录！ |
|
