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

JING Tian; WANG Xiangqi; WANG Qun; WU Hongli; GONG Xiaodong

doi:10.11804/NuclPhysRev.30.04.503

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Article Navigation > Nuclear Physics Review > 2013 > 30(4): 503-510

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

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

doi: 10.11804/NuclPhysRev.30.04.503

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

Received Date: 1900-01-01
Rev Recd Date: 1900-01-01
Publish Date: 2013-12-20

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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沈阳化工大学材料科学与工程学院沈阳 110142

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

doi: 10.11804/NuclPhysRev.30.04.503

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

Received Date: 1900-01-01
Rev Recd Date: 1900-01-01
Publish Date: 2013-12-20

Key words:

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.

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