Analytical representation of the solution of the space kinetic diffusion equation in a one-dimensional and homogeneous domain

Authors

  • Fernanda Tumelero Programa de Pós-Graduação em Engenharia Mecânica (PROMEC) Universidade Federal do Rio Grande do Sul (UFRGS)
  • Celso M. F. Lapa Instituto de Engenharia Nuclear (IEN)/CNEN
  • Bardo E. J Bodmann Programa de Pós-Graduação em Engenharia Mecânica (PROMEC) Universidade Federal do Rio Grande do Sul (UFRGS)
  • Marco T. Vilhena Programa de Pós-Graduação em Engenharia Mecânica (PROMEC) Universidade Federal do Rio Grande do Sul (UFRGS)

DOI:

https://doi.org/10.15392/bjrs.v7i2B.389

Keywords:

neutron diffusion equation, Taylor series, modified Adomian Decomposition method

Abstract

In this work we solve the space kinetic diffusion equation in a one-dimensional geometry considering a homogeneous domain, for two energy groups and six groups of delayed neutron precursors. The proposed methodology makes use of a Taylor expansion in the space variable of the scalar neutron flux (fast and thermal) and the concentration of delayed neutron precursors, allocating the time dependence to the coefficients. Upon truncating the Taylor series at quadratic order, one obtains a set of recursive systems of ordinary differential equations, where a modified decomposition method is applied. The coefficient matrix is split into two, one constant diagonal matrix and the second one with the remaining time dependent and off-diagonal terms. Moreover, the equation system is reorganized such that the terms containing the latter matrix are treated as source terms. Note, that the homogeneous equation system has a well known solution, since the matrix is diagonal and constant. This solution plays the role of the recursion initialization of the decomposition method. The recursion scheme is set up in a fashion where the solutions of the previous recursion steps determine the source terms of the subsequent steps. A second feature of the method is the choice of the initial and boundary conditions, which are satisfied by the recursion initialization, while from the first recursion step onward the initial and boundary conditions are homogeneous. The recursion depth is then governed by a prescribed accuracy for the solution.

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References

ADOMIAN, G. A review of the decomposition method in applied mathematics. Journal of Math-ematical Analysis and Applications, v.135, p. 501-544, 1988.

ADOMIAN, G. Solving Frontier Problems of Physics: The Decomposition Method. Springer Netherlands, 1994.

ADOMIAN, G.; RACH, R. Modified Adomian polynomials. Mathematical and Computer Mod-elling, v. 24, p. 39-46, 1996.

CEOLIN, C. Solução Analítica da Equação Cinética de Difusão Multigrupo de Nêutrons em Geometria Cartesiana Unidimensional Pela Técnica da Transformada Integral. UFRGS, Dis-sertação de Mestrado, Porto Alegre/RS, 2010.

CEOLIN, C.; VILHENA, M. T.; BODMANN, B. E. J.; ALVIM, A. C. M. On the Analytical So-lution of the Multi Group Neutron Diffusion Kinetic Equation in a Multilayered Slab, In: INTER-NATIONAL NUCLEAR ATLANTIC CONFERENCE, 2011, Belo Horizonte. Annals… Belo Horizonte: Comissão Nacional de Energia Nuclear, 2011.

CEOLIN, C.; SCHRAMM, M.; VILHENA, M. T.; BODMANN, B. E. J. On an evaluation of the continuous flux and dominant eigenvalue problem for the steady state multi-group multi-layer neu-tron diffusion equation, In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, 2013, Recife. Annals... Recife: Comissão Nacional de Energia Nuclear, 2013.

CEOLIN, C.; SCHRAMM, M.; BODMANN, B. E. J.; VILHENA, M. T.; LEITE, D. Q. On an analytical evaluation of the flux and dominant eigenvalue problem for the steady state multi-group multi-layer neutron diffusion equation. Kerntechnik, v. 79, p. 430-435, 2014.

CEOLIN, C. A equação unidimensional de difusão de nêutrons com modelo multigrupo de energia e meio heterogêneo: avaliação do fluxo para problemas estacionários e de cinética. PROMEC/UFRGS, Tese de Doutorado, Porto Alegre/RS, 2014.

CEOLIN, C.; SCHRAMM, M.; VILHENA, M. T.; BODMANN, B. E. J. On the Neutron multi-group kinetic diffusion equation in a heterogeneous slab: An exact solution on a finite set of discrete points. Annals of Nuclear Energy, v. 76, p. 271-282, 2015.

CEOLIN, C.; SCHRAMM, M.; BODMANN, B. E. J.; VILHENA, M. T. On progress of the solu-tion of the stationary 2-dimensional neutron diffusion equation: A polynomial approximation meth-od with error analysis, In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, 2015, São Paulo. Annals... São Paulo: Comissão Nacional de Energia Nuclear, 2015.

PETERSEN, C. Z. Solução Analítica das equações da Cinética Pontual e Espacial da Teoria de Difusão de Nêutrons pelas técnicas da GITT e Decomposição. PROMEC/UFRGS, Tese de Dou-torado, Porto Alegre/RS, 2011.

PETERSEN, C. Z.; DULLA, S.; VILHENA, M. T.; RAVETTO, P.; BODMANN, B. On the Ana-lytical Solution of the Multigroup Neutron Kinetics Diffusion Equations in Homogeneous Parallele-piped, In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, 2011, Belo Horizon-te. Annals.. Belo Horizonte: Comissão Nacional de Energia Nuclear, 2011.

SCHRAMM, M. An algorithm to multi-group two-dimensional neutron diffusion kinetics in nuclear reactors cores. PROMEC/UFRGS, Tese de Doutorado, Porto Alegre/RS,2016.

SILVA, M. W.; LEITE, S. B.; VILHENA, M. T.; BODMANN, B. E. J. On an analytical represen-tation for the solution of the neutron point kinetics equation free of stiffness. Annals of Nuclear Energy, v.71, p. 97-102, 2014.

TUMELERO, F. Solução das equações da cinética pontual de nêutrons com e sem retroalimen-tação de temperatura pelo método da aproximação polinomial. PPGMMAT/UFPel, Dissertação de Mestrado, Pelotas/RS, 2015.

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Published

2019-06-25

Issue

Section

XX Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XX ENFIR)

How to Cite

Analytical representation of the solution of the space kinetic diffusion equation in a one-dimensional and homogeneous domain. Brazilian Journal of Radiation Sciences, Rio de Janeiro, Brazil, v. 7, n. 2B (Suppl.), 2019. DOI: 10.15392/bjrs.v7i2B.389. Disponível em: https://www.bjrs.org.br/revista/index.php/REVISTA/article/view/389.. Acesso em: 9 may. 2024.

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