华电技术 ›› 2012, Vol. 34 ›› Issue (7): 4-7.

• 专题综述 • 上一篇    下一篇

AP 1000堆芯余热导出系统的分析与研究

张军承   

  1. 国核工程有限公司,上海200233
  • 收稿日期:1900-01-01 修回日期:1900-01-01 出版日期:2012-07-25 发布日期:2012-07-25

Analysis and research on residual heat removal system of AP 1000 core

ZHANG Juncheng   

  1. State Nuclear Power Engineering Company, Shanghai 200233, China
  • Received:1900-01-01 Revised:1900-01-01 Online:2012-07-25 Published:2012-07-25

摘要: 介绍了AP 1000第3代核电堆芯冷却技术的先进性和可靠性,论述了核反应堆堆芯余热产生的机制,对AP 1000停堆冷却系统的设计特点、控制策略进行了分析研究,阐明了AP 1000设计的堆芯冷却技术能够满足核安全要求并代表了一种具有前瞻性的设计理念。

关键词: AP 1000, 余热导出系统, 堆芯冷却, 控制策略

Abstract: the advancement and the reliability of third generation AP 1000 power reactor core cooling technology were introduced. The generating mechanism of the residual heat in the reactor core was expounded. The design features and the control strategy of the shutdown and cooling system of AP 1000 were analyzed and researched. It was expounded that the AP 1000 core cooling technology can satisfy the nuclear safety requirement and represents a forwardlooking design concept.

Key words: AP 1000 pressurized water reactor, power reactor core cooling technology, residual heat removal system, control strategy