Analysis of Effect of Steam-Line Break Accident on Core of Ling'ao Unit 1 Cycle 3

In the specific reload safety evaluations in Daya Bay and Ling’ao nuclear power stations,the steam line break（SLB） accident often resulted in the core parameters exceeding the safety limits during recent years.This leads to the reanalysis of SLB accident.Therefore,the analysis of effects of SLB on core is very important in the reload design in Daya Bay and Ling’ao nuclear power stations.This paper presents the analysis of the effect of SLB on core for Ling’ao unit 1 cycle 3,based on the Framatome ANP core design procedure manual.The analytical results show that,the core designed by DMNC for Ling’ao unit 1 cycle 3 is safe,during the SLB accident.