CAJ | 학술논문

加速器驱动的次临界系统（ADS ）由于外中子源的存在导致堆芯中子通量密度分布强烈的各向异性，须采用中子输运方法进行计算。采用蒙特卡罗输运耦合燃耗方法进行设计计算效率很低，而传统反应堆两步法中堆芯计算采用中子扩散方法，对ADS并不适用。为此，开发了两步法堆芯确定论输运的次临界系统中子学分析程序，第1步组件计算采用超细群共振组件程序，产生堆芯计算所需的少群均匀化参数；第2步堆芯计算采用三维三角形离散坐标节块输运程序DN T R进行中子学计算，堆芯燃耗采用微观燃耗的方法进行计算。通过对多栅元燃耗、BN600基准题以及ADS均匀装料模型计算检验，表明该程序具有良好的计算精度和计算效率。
가속기구동적차림계계통（ADS ）유우외중자원적존재도치퇴심중자통량밀도분포강렬적각향이성，수채용중자수운방법진행계산。채용몽특잡라수운우합연모방법진행설계계산효솔흔저，이전통반응퇴량보법중퇴심계산채용중자확산방법，대ADS병불괄용。위차，개발료량보법퇴심학정론수운적차림계계통중자학분석정서，제1보조건계산채용초세군공진조건정서，산생퇴심계산소수적소군균균화삼수；제2보퇴심계산채용삼유삼각형리산좌표절괴수운정서DN T R진행중자학계산，퇴심연모채용미관연모적방법진행계산。통과대다책원연모、BN600기준제이급ADS균균장료모형계산검험，표명해정서구유량호적계산정도화계산효솔。
The neutron flux density distribution of the accelerator driven subcritical system (ADS) is strongly anisotropic because of the external neutron source and thus neutron transport calculation is necessary . The Monte Carlo transport coupled with burnup calculation method is not efficient enough to be applied to the design work of ADS ,and the traditional two-step reactor analysis method with the neutron diffusion method is not suitable . Therefore , the two-step ADS analysis code with the deterministic transport method was developed . The first step was carried out by the lattice code with the hyper-fine group resonance calculation method to provide the few-group homogenized parameters for the core calculation .The second step was executed by the three-dimensional discrete ordinates nodal transport calculation code (DNTR) in triangular meshes .The micro-depletion method was used for the burnup calculation of the core .The code was validated by a multi-cell burnup problem ,the BN600 benchmark and the uniformly fuelled ADS model . The numerical results indicate that the code FM ADS is reliable and efficient .