| ADS次临界堆脉冲中子源实验动态特性数值模拟研究 |
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| 引用本文： | 谢芹,谢金森,曾文杰,何丽华,刘紫静,于涛.ADS次临界堆脉冲中子源实验动态特性数值模拟研究[J].南华大学学报(自然科学版),2015,29(3):1-5. |
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| 作者姓名： | 谢芹 谢金森 曾文杰 何丽华 刘紫静 于涛 |
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| 作者单位： | 湖南省核燃料循环技术与装备协同创新中心,湖南 衡阳 421001;南华大学 核科学技术学院,湖南 衡阳 421001,湖南省核燃料循环技术与装备协同创新中心,湖南 衡阳 421001;南华大学 核科学技术学院,湖南 衡阳 421001;中国原子能科学研究院反应堆工程研究所,北京 102413,湖南省核燃料循环技术与装备协同创新中心,湖南 衡阳 421001;南华大学 核科学技术学院,湖南 衡阳 421001,湖南省核燃料循环技术与装备协同创新中心,湖南 衡阳 421001;南华大学 核科学技术学院,湖南 衡阳 421001,湖南省核燃料循环技术与装备协同创新中心,湖南 衡阳 421001;南华大学 核科学技术学院,湖南 衡阳 421001;中国原子能科学研究院反应堆工程研究所,北京 102413,湖南省核燃料循环技术与装备协同创新中心,湖南 衡阳 421001;南华大学 核科学技术学院,湖南 衡阳 421001 |
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| 基金项目： | 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 |
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| 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.
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| 关 键 词： | 加速器驱动次临界系统 脉冲中子源实验 MCNPX程序 |
| 收稿时间： | 2015/4/25 0:00:00 |
Numerical Simulation of Dynamic Characteristic in Accelerator Driven System Sub-critical Reactor Pulse Neutron Source Experiments |
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| XIE Qin,XIE Jin-sen,ZHENG Wen-jie,HE Li-hu,LIU Zi-jing and YU Tao.Numerical Simulation of Dynamic Characteristic in Accelerator Driven System Sub-critical Reactor Pulse Neutron Source Experiments[J].Journal of Nanhua University:Science and Technology,2015,29(3):1-5. |
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| Authors: | XIE Qin XIE Jin-sen ZHENG Wen-jie HE Li-hu LIU Zi-jing and YU Tao |
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| Institution: | Hunan Cooperative Innovation Center for Nuclear Fuel Cycle Technology & Equipment,Hengyang,Hunan 421001,China;School of Nuclear Science and Technology,University of South China,Hengyang,Hunan 421001,China,Hunan Cooperative Innovation Center for Nuclear Fuel Cycle Technology & Equipment,Hengyang,Hunan 421001,China;School of Nuclear Science and Technology,University of South China,Hengyang,Hunan 421001,China;Department of Reactor Engineering Research and Design,China Institute of Atomic Energy,Beijing 102413,China,Hunan Cooperative Innovation Center for Nuclear Fuel Cycle Technology & Equipment,Hengyang,Hunan 421001,China;School of Nuclear Science and Technology,University of South China,Hengyang,Hunan 421001,China,Hunan Cooperative Innovation Center for Nuclear Fuel Cycle Technology & Equipment,Hengyang,Hunan 421001,China;School of Nuclear Science and Technology,University of South China,Hengyang,Hunan 421001,China,Hunan Cooperative Innovation Center for Nuclear Fuel Cycle Technology & Equipment,Hengyang,Hunan 421001,China;School of Nuclear Science and Technology,University of South China,Hengyang,Hunan 421001,China;Department of Reactor Engineering Research and Design,China Institute of Atomic Energy,Beijing 102413,China and Hunan Cooperative Innovation Center for Nuclear Fuel Cycle Technology & Equipment,Hengyang,Hunan 421001,China;School of Nuclear Science and Technology,University of South China,Hengyang,Hunan 421001,China |
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| Abstract: | Drive by intense external neutron sources and the deep subcritical levels make Accelerator 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 experiments in the fast/thermal-combined ADS system facility (YLINA-Booster expermental facilty) 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. |
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| Keywords: | accelerator driven subcritical system pulse neutron source experiment MCNPX code |
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