华龙一号蒸汽发生器传热管6 mm破口事故放射性后果分析  

Radiological Consequence Analysis of a 6mm Diameter Break on HPR1000 Steam Generator Heat Transfer Tube

作　　者：刘建昌 陈韵茵 陈忆晨 沈永刚 卢向晖 Liu Jianchang;Chen Yunyin;Chen Yichen;Shen Yonggang;Lu Xianghui(China Nuclear Power Technology Research Institute Co.,Ltd,Shen Zhen 518000,China)

机构地区：[1]中广核研究院有限公司,深圳518000

出　　处：《核安全》2022年第2期38-42,共5页Nuclear Safety

摘　　要：当蒸汽发生器传热管发生6 mm的小破口时,在控制系统的作用下,一、二回路热工水力参数将不会触发热工保护信号。在瞬态过程中,带放射性的一回路冷却剂通过破口进入二回路系统,导致二回路放射性水平升高,触发二回路放射性高报警系统,操纵员根据放射性报警信号采取相应的缓解手段,将机组后撤到安全停堆状态。本文采用CATHARE程序开展了热工水力分析,结合分析结果,采用保守的源项分析方法,评价了该事故瞬态导致的放射性后果。分析结果表明,通过放射性报警信号,操纵员及时识别并隔离破损的蒸汽发生器(SG),瞬态过程不会对公众造成严重的放射性后果。When a 6 mm diameter break occurs on the steam generator(SG) heat transfer tube, the thermal-hydraulic safety signals cannot be triggered due to the operation of the control system. During the transient, the contaminated primary coolant transfer to the secondary side of affected steam generator(SGa)through the break, causing the activity increase on the SGa. The radioactivity high signals of the secondary side are triggered. Mitigation actions are taken by operators to bring the reactor to safety shutdown states.In the present paper, the accident is analyzed using CATHARE code. The transient analysis results are used to evaluate the source terms released to the environment and corresponding radiological consequence on the public. The results show that SGa can be identified and isolated manually in time. The radiological release to the environment during the transient is limited.

关 键 词：SGTR 源项 放射性后果 

分 类 号：TL383[核科学技术—核技术及应用]