SGTR事故SG满溢分析扩展研究  

Expansion Research of SG Overfill Analysis for SGTR

作　　者：刘立欣[1] 刘展[1] Liu Lixin;Liu Zhan(Shanghai Nuclear Engineering Research and Design Institute,Shanghai,200233,China)

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《核动力工程》2020年第3期81-85,共5页Nuclear Power Engineering

摘　　要：采用热工水力系统程序进行核电厂蒸汽发生器传热管破裂(SGTR)事故蒸汽发生器(SG)满溢分析,验证在该事故下SG不会发生满溢;对SGTR事故进行扩展研究,考虑多种传热管破裂情况,包括单根传热管双端断裂、多根传热管双端断裂和传热管破口,并将3种情况的分析结果进行比较,给出SGTR事故最极限的工况。研究结果表明,单根传热管双端断裂工况下,SG不会发生满溢,且与其他2种工况相比满溢裕量最小,在所有分析工况中最极限。Steam generator(SG) tube rupture overfill in a nuclear power plant have been analyzed with thermal-hydraulic system code, which validates that SG do not overfill under this accident. Expansion research of the overfill analysis for SGTR also has been conducted in this paper, considering multiple cases for tube break, including single tube double ended, multiple tubes double ended and tube small break. The analysis results of three cases are compared and the most conservative situation is provided in this paper. The results show that the case of single tube double ended is the most limit case, under which the SG overfill do not occur, and the overfill margin is less than that in the other two cases.

关 键 词：蒸汽发生器(SG)传热管破裂(SGTR) SG满溢 单根传热管双端断裂 传热管破口 

分 类 号：TL329[核科学技术—核技术及应用]