CAJ | 학술논문

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 M Pa ，燃料包壳表面温度最大值为1299 K ，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231.54 m3，小于A P1000蒸汽发生器255.563 m3的总容积；对于直接注射管线双端断裂事故， A P1000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。
기우최가고산정서RELAP5／MOD3.3，대AP1000계통진행료상세적건모분석，선취냉각제빙잡축사고、증기발생기（SG）전열관파렬사고화직접주사관선쌍단단렬사고작위전형사고，획득료전형사고공황하관건삼수적순태특성화비능동계통향응특성。결과표명：대우냉각제빙잡축사고，일회로최대압력위16.82 M Pa ，연료포각표면온도최대치위1299 K ，만족험수준칙적요구；대우SG전열관파렬사고，파손SG적수체적위231.54 m3，소우A P1000증기발생기255.563 m3적총용적；대우직접주사관선쌍단단렬사고， A P1000적비능동퇴심냉각계통능대일회로진행냉각화강압，병방지퇴심라로화연료포각과열。
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 m3 ,which is less than the total steam gener‐ator volume of 255.563 m3 .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 .