Neutron diffusion coefficient for disordered arrays of TRISO particles in spherical nuclear fuel

被引：2

作者：

Aguilar-Madera, C. G. ^{[1
]}

Herrera-Hernandez, E. C. ^{[2
]}

Espinosa-Paredes, G. ^{[3
]}

机构：

[1] Univ Autonoma Nuevo Leon, Fac Ciencias Tierra, Linares Nl 67700, Mexico

[2] CONACYT, Ctr Ingn & Desarrollo Ind, Ciudad del Carmen 24150, Campeche, Mexico

[3] Univ Autonoma Metropolitana Iztapalapa, Area Ingn Recursos Energet, Cd Mexico 09340, Mexico

来源：

ANNALS OF NUCLEAR ENERGY | 2020年 / 146卷

关键词：

PBMR; TRISO particles; Up-scaled method; Closure Problem; Neutron diffusion coefficients; Stochastic process; Ensemble realizations; MASS-TRANSFER; TRANSPORT;

D O I：

10.1016/j.anucene.2020.107635

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The aim of this paper is the analysis of the neutron diffusion coefficient with 3D approximation of the up-scaled neutron diffusion equation. In this work we present comparisons of 3D ordered and disordered approximations. To this end, we compute the effective diffusion and interfacial neutronic flux coefficients in representative cells of fuel elements composed by several TRISO particles randomly collocated. The ensemble of 700 realizations, show more variations in the numerical estimation of the interfacial neutronic flux coefficient than for the effective diffusion coefficient. The assumption of one ordered arrangement of TRISO particles inside the fuel particle is enough for estimation of the diffusion coefficient. A comparison of the upscaled model with effective coefficients computed from disordered arrangements, with analytical solutions for unidirectional neutron diffusion demonstrates that the classical diffusion theory and the Boltzmann equation would yield similar predictions for long times and highly or poorly absorbent materials. (C) 2020 Elsevier Ltd. All rights reserved.

引用

页数：10

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