一体化小型堆安全壳抽真空试验研究  

Study on the Vacuum Extraction Test for the Containment of the Integrated Small Reactor

作　　者：刘洋 LIU Yang(Shanghai Nuclear Engineering Research&Design Institute Co.,Ltd.,Shanghai 200233,China)

机构地区：[1]上海核工程研究设计院股份有限公司,上海200233

出　　处：《中国核电》2024年第6期893-896,共4页China Nuclear Power

摘　　要：一体化小型堆作为可为核能供热的新型堆型,其各项试验研究可以为类似堆型提供参考,通过对一体化小型堆的设计构想及传统电厂的调试方法研究,提出一体化小型堆安全壳试验可采用抽真空试验等方式验证安全壳及配套系统功能,同时对安全壳抽真空试验等试验验收准则提出了建议,以期为一体化小型堆安全壳试验及类似电厂安全壳试验提供参考。Serving as a novel model for nuclear-powered heating,the integrated small reactor offers insights for analogous reactors via its experimental research.Drawing from the design philosophies of integrated small reactors and exploring commissioning techniques of traditional power plant,it is suggested that the containment tests for these reactors can employ vacuum testing to validate the functions of the containment vessel and its supporting systems.Additionally,recommendations are provided for the acceptance criteria of containment vessel vacuum tests,aiming to serve as a guideline for both integrated small reactors and similar power plants.

关 键 词：一体化小型堆 安全壳 抽真空 验收准则 

分 类 号：TM623[电气工程—电力系统及自动化]