摘要
基于最佳估算程序RELAP5/MOD3.3,对AP1000系统进行了详细的建模分析,选取冷却剂泵卡轴事故、蒸汽发生器(SG)传热管破裂事故和直接注射管线双端断裂事故作为典型事故,获得了典型事故工况下关键参数的瞬态特性和非能动系统响应特性。结果表明:对于冷却剂泵卡轴事故,一回路最大压力为16.82 MPa,燃料包壳表面温度最大值为1 299K,满足验收准则的要求;对于SG传热管破裂事故,破损SG的水体积为231.54m3,小于AP1000蒸汽发生器255.563m3的总容积;对于直接注射管线双端断裂事故,AP1000的非能动堆芯冷却系统能对一回路进行冷却和降压,并防止堆芯裸露和燃料包壳过热。
The best‐estimate code RELAP5/MOD3.3 was used to simulate the transient characteristics of reactor coolant pump shaft seizure accident ,steam generator tube rup‐ture accident and double‐ended direct vessel injection line accident for the AP1000 sys‐tem .The key parameters of those transients and response of the passive system in those transients w ere show n in this paper . T he results indicate that the pressure of primary system could reach 16.82 M Pa and the peak temperature of the fuel cladding could be 1 299 K in the reactor coolant pump shaft seizure accident ,which meets the require‐ments of acceptance criteria of this accident .In steam generator tube rupture accident , water volume of the ruptured SG is 231.54 m^3 ,which is less than the total steam gener‐ator volume of 255.563 m^3 .For the double‐ended direct vessel injection line accident , the passive core cooling system is able to cool dow n and depressurize the primary sys‐tem ,and prevent the core uncovery and fuel cladding heatup .
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2015年第4期646-653,共8页
Atomic Energy Science and Technology
基金
国家科技重大专项资助项目(2011ZX06002-010
2013ZX06002-001)
