CAJ | 학술논문

行波堆是一种能够实现自持增殖和燃耗革新概念的先进反应堆系统。根据泰拉能源公司最新设计的钠冷行波堆泰拉能源一号的具体参数，建立泰拉能源一号1／6堆芯物理模型，利用 FLUENT 软件的用户接口（UDF／UDS），开发点堆中子动力模型的计算程序和模块，用于计算堆芯的功率；利用 FLUENT 软件中的多孔介质模型模拟堆芯三维流场；再将两者耦合起来进行计算，研究行波堆的物理热工耦合和安全特性。进行稳态运行工况计算和反应性引入事故瞬态计算，计算结果表明：稳态的计算结果与设计值吻合得比较好；根据瞬态计算结果，在设计的反应性引入事故瞬态工况下，如果不启用停堆保护系统，泰拉能源一号也是安全的。
행파퇴시일충능구실현자지증식화연모혁신개념적선진반응퇴계통。근거태랍능원공사최신설계적납랭행파퇴태랍능원일호적구체삼수，건립태랍능원일호1／6퇴심물리모형，이용 FLUENT 연건적용호접구（UDF／UDS），개발점퇴중자동력모형적계산정서화모괴，용우계산퇴심적공솔；이용 FLUENT 연건중적다공개질모형모의퇴심삼유류장；재장량자우합기래진행계산，연구행파퇴적물리열공우합화안전특성。진행은태운행공황계산화반응성인입사고순태계산，계산결과표명：은태적계산결과여설계치문합득비교호；근거순태계산결과，재설계적반응성인입사고순태공황하，여과불계용정퇴보호계통，태랍능원일호야시안전적。
Traveling-wave reactor (TWR)is an advanced reactor system of innovative concept which can achieve self-sustaining propagation and burn-up.This study establishes one-sixth model of the whole reactor core based on the specific parameters of so-dium cooled TWR TP-1 which is the latest design of the Terra Power Energy Company.The program module of the point reactor kinetic model is developed to calculate the core power by using FLUENT user interface (UDF/UDS).The three-dimensional flow field of the reactor core is simulated with the porous media model.Coupling the above two,the characteristics of the neutronics and thermal-hydraulics coupling and safety in TWR are investigated.Two operation conditions are calculated:one steady condi-tion and one transient condition,i.e.reactivity-insertion accident.The calculation results of the steady condition show good agreement with TP-1 design values.In the reactivity-insertion accident,if the shutdown protection system is not running,TP-1 would be safe.