加速器驱动次临界系统中非齐次中子扩散方程的一种解析解(英文)

井田; 王相綦; 王群; 武红利; 龚晓冬

doi:10.11804/NuclPhysRev.30.04.503

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加速器驱动次临界系统中非齐次中子扩散方程的一种解析解(英文)

井田, 王相綦, 王群, 武红利, 龚晓冬

文章导航 > 原子核物理评论 > 2013 > 30(4): 503-510

井田, 王相綦, 王群, 武红利, 龚晓冬. 加速器驱动次临界系统中非齐次中子扩散方程的一种解析解(英文)[J]. 原子核物理评论, 2013, 30(4): 503-510. doi: 10.11804/NuclPhysRev.30.04.503

引用本文:

JING Tian, WANG Xiangqi, WANG Qun, WU Hongli, GONG Xiaodong. An Analytical Solution to Inhomogeneous Neutron Diffusion Equation in Accelerator Driven System[J]. Nuclear Physics Review, 2013, 30(4): 503-510. doi: 10.11804/NuclPhysRev.30.04.503

Citation:

JING Tian, WANG Xiangqi, WANG Qun, WU Hongli, GONG Xiaodong. An Analytical Solution to Inhomogeneous Neutron Diffusion Equation in Accelerator Driven System[J]. Nuclear Physics Review, 2013, 30(4): 503-510. doi: 10.11804/NuclPhysRev.30.04.503

加速器驱动次临界系统中非齐次中子扩散方程的一种解析解(英文)

doi: 10.11804/NuclPhysRev.30.04.503

中国科技大学国家同步辐射实验室,安徽合肥230029;
中国科技大学近代物理系,安徽合肥230027

An Analytical Solution to Inhomogeneous Neutron Diffusion Equation in Accelerator Driven System

National Synchrotron Radiation Laboratory, University of Science and Technology of China, Hefei 230029, China;

摘要: 利用傅里叶方法得到了非齐次中子扩散方程格林函数的解析形式，通过格林函数计算了当外源在堆芯任意位置时的中子通量密度分布，分析了在次临界反应堆系统中，次临界倍增系数ks 与外源位置和相同次临界深度下堆芯尺寸的依赖关系。发现，ks 随着堆芯尺寸的增加而减小，这点变化虽小，但能量增益对ks 以及堆芯尺寸是相当敏感的，加速器驱动的次临界系统(ADS) 设计时应必须予以考虑。The analytical form of the Green’s functions of the inhomogeneous diffusion equation for neutrons are obtained using the Fourier method. The neutron flux distributions with the external neutron source locatedat arbitrary positions are calculated from the Green’s functions. In a subcritical system, the ependences of the subcritical multiplication factor ks on the source position and the core size with the fixed subcriticality keff are analyzed based on the series solution. It is found that ks decreases with the core size. Although this variation is small, the energy gain is sensitive to ks and then the core size, which has to be taken into account in the design of the source driven subcritical system.
- ADS /
- 中子通量密度 /
- 中子扩散方程 /
- 次临界倍增系数 /
- 次临界度
Abstract: The analytical form of the Green’s functions of the inhomogeneous diffusion equation for neutrons are obtained using the Fourier method. The neutron flux distributions with the external neutron source locatedat arbitrary positions are calculated from the Green’s functions. In a subcritical system, the ependences of the subcritical multiplication factor ks on the source position and the core size with the fixed subcriticality keff are analyzed based on the series solution. It is found that ks decreases with the core size. Although this variation is small, the energy gain is sensitive to ks and then the core size, which has to be taken into account in the design of the source driven subcritical system.
- ADS /
- neutron flux /
- neutron diffusion equation /
- subcritical multiplication factor /
- subcriticality

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加速器驱动次临界系统中非齐次中子扩散方程的一种解析解(英文)

doi: 10.11804/NuclPhysRev.30.04.503

中国科技大学国家同步辐射实验室,安徽合肥230029;

中国科技大学近代物理系,安徽合肥230027

收稿日期: 1900-01-01
修回日期: 1900-01-01
刊出日期: 2013-12-20

关键词:

ADS /

摘要: 利用傅里叶方法得到了非齐次中子扩散方程格林函数的解析形式，通过格林函数计算了当外源在堆芯任意位置时的中子通量密度分布，分析了在次临界反应堆系统中，次临界倍增系数ks 与外源位置和相同次临界深度下堆芯尺寸的依赖关系。发现，ks 随着堆芯尺寸的增加而减小，这点变化虽小，但能量增益对ks 以及堆芯尺寸是相当敏感的，加速器驱动的次临界系统(ADS) 设计时应必须予以考虑。The analytical form of the Green’s functions of the inhomogeneous diffusion equation for neutrons are obtained using the Fourier method. The neutron flux distributions with the external neutron source locatedat arbitrary positions are calculated from the Green’s functions. In a subcritical system, the ependences of the subcritical multiplication factor ks on the source position and the core size with the fixed subcriticality keff are analyzed based on the series solution. It is found that ks decreases with the core size. Although this variation is small, the energy gain is sensitive to ks and then the core size, which has to be taken into account in the design of the source driven subcritical system.