On the Neutron multi-group kinetic diffusion equation in a heterogeneous slab: An exact solution on a finite set of discrete points

Author:

Ceolin Celina,Schramm Marcelo,Vilhena Marco T.,Bodmann Bardo E.J.

Funder

Conselho Nacional de Desenvolvimento Científico e Tecnológico (CNPq, Brazil)

Coordenação de Aperfeiçoamento de Pessoal de Nível Superior (CAPES, Brazil)

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference14 articles.

1. Breaking the limits: the Taylor series method;Barrio;Appl. Math. Comput.,2011

2. Elementary Differential Equations and Boundary Value Problems;Boyce,2001

3. Ceolin, C., Schramm, M., Vilhena, M.T., Bodmann, B.E.J., 2013. On an Evaluation of the Continuous Flux and Dominant Eigenvalue Problem for the Steady State Multi-Group Multi-Layer Neutron Diffusion Equation. International Nuclear Atlantic Conference - INAC, Recife, PE-Brazil.

4. Solving ordinary differential equations using Taylor series;Corliss;ACM Transact. Math. Softw.,1982

5. Neutron Transport Theory;Davison,1957

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