Averaging the neutron diffusion equation

doi:10.1016/j.pnucene.2008.10.007

2009-04-01

PRE

R. Vázquez-Rodríguez

Gilberto Espinosa-Paredes *

Jaime B. Morales-Sandoval

A. Vázquez–Rodríguez

E.-G. Espinosa–Martínez

DOI：10.1016/j.pnucene.2008.10.007

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摘要

En 中文

This paper presents a general theoretical analysis of the neutron motion problem in a nuclear reactor, where large variations on neutron cross-sections normally preclude the use of the classical neutron diffusion equation. A volume-averaged neutron diffusion equation (VANDE) is derived which includes correction terms to diffusion and nuclear reaction effects. A method is presented to determine closure-relationships for the VANDE (e.g., effective diffusivity). In order to describe the distribution of neutrons in a highly heterogeneous configuration, it was necessary to extend the classical neutron diffusion equation. Thus, the averaged diffusion equation includes two correction factors: the first correction is related with the absorption process of the neutron and the second correction is a contribution to the neutron diffusion, both parameters are related to neutron effects on the interface of a heterogeneous configuration. As an example of the VANDE, the plane source in an infinite medium was considered to study the effects of the correction factors on the neutron flux, and the results were compared with classic solution. (C) 2008 Elsevier Ltd. All rights reserved.

Keyword:

Diffusion equation

Averaging volume

Highly heterogeneous

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期刊

Progress in Nuclear Energy

IF:

3.2

论文数:

5.6K

被引数:

10.0K

机构

Universidad Nacional Autonoma de Mexico

学者数:

3.8W

论文数: 2.6W

被引数: 28

universidad autonoma metropolitana - mexico

学者数:

5.8K

论文数: 4.4K

被引数: 4

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