CAJ | 학술논문

为有效解决大型复杂核设施屏蔽计算问题，研究了三维蒙特卡罗（MC）-离散纵标（SN ）双向耦合方法，通过自主开发接口程序实现MC粒子概率分布与SN 角通量密度之间的相互转换，实现MC-SN 双向耦合计算。将基于MC-SN 双向耦合方法的程序用于某反应堆堆坑底部粒子注量率计算。利用MC程序建立堆芯及堆坑处的精细模型进行计算，三维SN 程序用于堆芯下表面与压力容器底面之间区域的计算。通过MC-SN-MC两步耦合计算，给出堆坑通道及小室内的中子和光子注量率。三维MC-SN 双向耦合方法计算结果与单一MCNP程序结果吻合较好，初步验证了该方法是解决大型复杂核装置屏蔽问题的有效工具。
위유효해결대형복잡핵설시병폐계산문제，연구료삼유몽특잡라（MC）-리산종표（SN ）쌍향우합방법，통과자주개발접구정서실현MC입자개솔분포여SN 각통량밀도지간적상호전환，실현MC-SN 쌍향우합계산。장기우MC-SN 쌍향우합방법적정서용우모반응퇴퇴갱저부입자주량솔계산。이용MC정서건립퇴심급퇴갱처적정세모형진행계산，삼유SN 정서용우퇴심하표면여압력용기저면지간구역적계산。통과MC-SN-MC량보우합계산，급출퇴갱통도급소실내적중자화광자주량솔。삼유MC-SN 쌍향우합방법계산결과여단일MCNP정서결과문합교호，초보험증료해방법시해결대형복잡핵장치병폐문제적유효공구。
In order to effectively solve the shielding problem with complex geometric and bulk shields of nuclear facility ,the three-dimensional Monte Carlo (MC)-discrete ordi-nates (SN ) bidirectional coupled method was developed .The transform between particle probability distribution of MC and angle flux density of SN was realized by a self-devel-oped interface program to achieve the coupling calculation . The test calculation was taken by the application of the MC-SN bidirectional coupled method on the particle fluence rate calculation of reactor pit bottom .Monte Carlo code was employed to accu-rately simulate the structure of core and the model of reactor pit ,while the 3D SN code was used for the calculation from the core bottom surface to the pressure vessel bottom region .Neutron and photon fluence rates of reactor pit channel and indoor were calcu-lated by MC-SN-MC two step coupled method .The calculation results were compared with results of MCNP and satisfactory agreements were obtained .The results demon-strate that the method is an effective tool to solve the shielding problem of large complex shielding of nuclear facility .