CAJ | 학술논문

利用美国核管制委员会(US NRC)堆芯三维中子动力学软件 PARCS、热工水力软件 TRACE、辅助建模软件 SNAP 以及具有国内自主知识产权的压水堆燃料组件计算软件 RONBIN,建立了秦山二期两环路压水堆物理模型和热工水力系统模型,进行弹棒事故模拟计算,得出合理的计算结果.AFA 3G 燃料组件的两维中子输运计算由 ROBIN 程序完成,生成的宏观中子截面参数被传递给 PARCS 程序作为输入.然后由 PARCS 程序进行堆芯三维弹棒模拟计算,得到事故过程中的核功率变化趋势.最后将反应堆功率瞬态数据输入 TRACE 热工水力系统模型计算系统压力响应以及燃料包壳和芯块温度.本文通过使用与设计单位完全不同的软件体系,独立地验证了该堆型在弹棒事故下的安全性.
이용미국핵관제위원회(US NRC)퇴심삼유중자동역학연건 PARCS、열공수력연건 TRACE、보조건모연건 SNAP 이급구유국내자주지식산권적압수퇴연료조건계산연건 RONBIN,건립료진산이기량배로압수퇴물리모형화열공수력계통모형,진행탄봉사고모의계산,득출합리적계산결과.AFA 3G 연료조건적량유중자수운계산유 ROBIN 정서완성,생성적굉관중자절면삼수피전체급 PARCS 정서작위수입.연후유 PARCS 정서진행퇴심삼유탄봉모의계산,득도사고과정중적핵공솔변화추세.최후장반응퇴공솔순태수거수입 TRACE 열공수력계통모형계산계통압력향응이급연료포각화심괴온도.본문통과사용여설계단위완전불동적연건체계,독입지험증료해퇴형재탄봉사고하적안전성.
The purpose of this paper is to provide an overview of the rod ejection accident (REA)simulation of the two-loop PWR of Qinshan II by using US NRC’s safety analysis code PARCS/TRACE/SNAP and domestic fuel assembly calculation code ROBIN.The 2D neutron transportation calculation of AFA3G fuel assembly is performed by using ROBIN code.Macro cross sections are obtained from ROBIN outputs and supplied to PARCS code as inputs.Then rod ejection accident is simulated by the PARCS 3D core neutronic model and the reactor power trend is calculated as output of PARCS simulation.Finally,the reactor power trend is input to TRACE thermal hydraulic system model,and the system pressure response is calculated as well as fuel pellet and cladding temperature.Both steady-state and transient calculation are carried out in this paper.The calculation result is reasonable and safety of the specific reactor design is independently verified by using the analysis code that is totally different from design codes.