ADS次临界堆脉冲中子源实验动态特性数值模拟研究  

Numerical Simulation of Dynamic Characteristic in Accelerator Driven System Sub-critical Reactor Pulse Neutron Source Experiments

作　　者：谢芹[1,2] 谢金森[1,2,3] 曾文杰[1,2] 何丽华[1,2] 刘紫静[1,2,3] 于涛[1,2] 

机构地区：[1]湖南省核燃料循环技术与装备协同创新中心,湖南衡阳421001 [2]南华大学核科学技术学院,湖南衡阳421001 [3]中国原子能科学研究院反应堆工程研究所,北京102413

出　　处：《南华大学学报（自然科学版）》2015年第3期1-5,共5页Journal of University of South China：Science and Technology

基　　金：国家自然科学基金资助项目(11305088);湖南省自然科学基金资助项目(14JJ2088);湖南省核燃料循环技术与装备协同创新中心资助

摘　　要：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.Drive by intense external neutron sources and the deep subcritical levels make Accelerator Driven Suberitieal reactor have agreat difference between traditional critical reactors in neutronics parameters. It, makes the deterministic neutronic calculation method could not be used in ADS subcritieal reactor calculating directly. In this paper,the pulse neutron source experiments in the fast/thermal-combined ADS system facility （YLINA-Booster expermental facihy） are simulated by Monte Carlo N-Particle eXtended （MCNPX） code. The simulation results 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.

关 键 词：加速器驱动次临界系统 脉冲中子源实验 MCNPX程序 

分 类 号：TL326[核科学技术—核技术及应用]