CAJ | 학술논문

强外源驱动与深次临界度使得ADS次临界反应堆在中子学特性上与传统临界堆有较大差异，确定论中子学计算方法难以直接应用于ADS次临界堆。本文采用MCNPX程序对“快热”耦合ADS装置YALINA-Booster的PNS实验进行了模拟，并将模拟与实验结果进行比较。结果表明：在不同的堆芯布置方案和不同脉冲中子源特性下，模拟结果与实验结果具有良好的一致性，验证采用MCNPX程序研究ADS次临界堆中子学动态特性的可行性。
강외원구동여심차림계도사득ADS차림계반응퇴재중자학특성상여전통림계퇴유교대차이，학정론중자학계산방법난이직접응용우ADS차림계퇴。본문채용MCNPX정서대“쾌열”우합ADS장치YALINA-Booster적PNS실험진행료모의，병장모의여실험결과진행비교。결과표명：재불동적퇴심포치방안화불동맥충중자원특성하，모의결과여실험결과구유량호적일치성，험증채용MCNPX정서연구ADS차림계퇴중자학동태특성적가행성。
Drive by intense external neutron sources and the deep subcritical levels make Ac-celerator Driven Subcritical reactor have a great difference between traditional critical reactors in neutronics parameters. It makes the deterministic neutronic calculation method could not be used in ADS subcritical reactor calculating directly. In this paper,the pulse neutron source ex-periments in the fast/thermal-combined ADS system facility ( YLINA-Booster expermental facilty) are simulated by Monte Carlo N-Particle eXtended (MCNPX) code. The simulation re-sults are compared with the results of detectors in the experiments. The results clearly indicate that in different reactor core layouts and different neutron source characteristics,the simulation results are in excellent agreement with the experiment,and the MCNPX code could be used to study ADS Subcritical reactor neutronics dynamic parameters.