中国核电
中國覈電
중국핵전
CHINA NUCLEAR POWER
2014年
3期
207-211
,共5页
长期冷却%硼浓度%大破口失水事故%CCFL
長期冷卻%硼濃度%大破口失水事故%CCFL
장기냉각%붕농도%대파구실수사고%CCFL
long-term cooling%boron concentration%large break LOCA%CCFL
文章采用先进的热工水力分析程序CATHAR，对百万千瓦级ACP1000核电厂冷段大破口失水事故冷热段同时安注时CCFL作用下的上腔室及堆芯的流动换热特性、硼浓度特性进行了研究，并分析了破损环路热段安注流量大小对堆芯冷却的影响。研究表明：在热段安注总流量为614 m3/h时，破损环路对应热段安注流量的不同，不会对流入堆芯冷却有较大影响，破损环路热段安注流量差异不会对堆芯冷却有较大影响；切换至同时安注后堆芯硼浓度很快与系统达到平衡。
文章採用先進的熱工水力分析程序CATHAR，對百萬韆瓦級ACP1000覈電廠冷段大破口失水事故冷熱段同時安註時CCFL作用下的上腔室及堆芯的流動換熱特性、硼濃度特性進行瞭研究，併分析瞭破損環路熱段安註流量大小對堆芯冷卻的影響。研究錶明：在熱段安註總流量為614 m3/h時，破損環路對應熱段安註流量的不同，不會對流入堆芯冷卻有較大影響，破損環路熱段安註流量差異不會對堆芯冷卻有較大影響；切換至同時安註後堆芯硼濃度很快與繫統達到平衡。
문장채용선진적열공수력분석정서CATHAR，대백만천와급ACP1000핵전엄랭단대파구실수사고랭열단동시안주시CCFL작용하적상강실급퇴심적류동환열특성、붕농도특성진행료연구，병분석료파손배로열단안주류량대소대퇴심냉각적영향。연구표명：재열단안주총류량위614 m3/h시，파손배로대응열단안주류량적불동，불회대류입퇴심냉각유교대영향，파손배로열단안주류량차이불회대퇴심냉각유교대영향；절환지동시안주후퇴심붕농도흔쾌여계통체도평형。
The flow heat transfer and boron concentration characteristics in the upper plenum and the core affected by CCFL during the phase of simultaneous hot and cold leg injection in case of cold leg large break LOCA for the ACP1000 NPP were studied using the advanced T-H code CATHARE, and the effects of the safety injection flowrate from the hot leg located in broken loop on the core cooling was also studied in the paper. The study showed that the core cooling would not be mostly affected by the hot leg flowrate in the broken loop if the total hot leg injection flowrate fixed at 614 m3/h, and the boron concentration in the core would balance with the system after switching to simultaneous hot and cold leg injection.
