| AP1000非能动堆芯冷却系统及系统设计瞬态研究 |
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| 引用本文： | 王志.AP1000非能动堆芯冷却系统及系统设计瞬态研究[J].中国核电,2011(3):195-206. |
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| 作者姓名： | 王志 |
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| 作者单位： | 中国核工业集团公司核电部; |
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| 摘 要： | AP1000在标准设计中革新性重大改进之一就是采用了独特的非能动堆芯冷却系统(PXS)。目前世界上在役核电厂和在建核电工程中,AP1000非能动堆芯冷却系统是第一个完全采用非能动手段来达到堆芯冷却、冷却剂补充以及限制放射性释放等安全功能的安全相关系统。文章结合AP1000非能动堆芯冷却系统设计与运行,应用包络方法对一些重要的设计瞬态进行研究分析,从而得出系统设计的合理性和系统功能实现的可行性,为自主研发ACP100、ACP600、ACP1000等第三代核电技术提供借鉴和参考。
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| 关 键 词： | AP1000 非能动 堆芯冷却 设计瞬态 |
Research of AP1000 passive core cooling system and system design transient |
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| WANG Zhi.Research of AP1000 passive core cooling system and system design transient[J].China Nuclear Power,2011(3):195-206. |
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| Authors: | WANG Zhi |
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| Affiliation: | WANG Zhi(Department of Nuclear Power,China National Nuclear Corporation,Beijing 100822,China) |
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| Abstract: | The loss of active core cooling system of the plant immediately relates to severe safety accident.A unique safety-related system,called the passive core cooling system(PXS),is applied in AP1000 standard design,since a special steel containment shell is adopted.The PXS utilizes passive means to achieve the reactor safety functions: core cooling,coolant make-up,and radioactivity release limiting.This report emphasizes on system function design,and then discusses system design transients by using the bounding ... |
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| Keywords: | AP1000 passive core-cooling design transient |
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