Analytical solution of the multigroup neutron diffusion equation coupled with an iterative method
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| Format: | Artículo científico |
| Sprache: | en |
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Sociedade Brasileira de Proteção Radiológica - SBPR
2022
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| _version_ | 1876472934044794880 |
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| author | Adilson Costa da Silva |
| author_facet | Adilson Costa da Silva |
| contents | Analytical solution of the multigroup neutron diffusion equation coupled with an iterative method Adilson Costa da Silva Aquilino Senra Martinez Rodrigo Costa Diniz Alessandro da Cruz Gonçalves Biología eigenvalue eigenvalue slab reactor slab reactor iterative method Many numerical methods are being used to solve the multigroup neutron diffusion equation for different types of nuclear reactors. These methods solve this equation quite accurately and determine the neutron flux and power distribution in the reactor as well as the eigenvalue of the reactor core. In this paper, we are proposing the integration of an analytical solution with an iterative method to determine the neutron flux distribution in the reactor and the effective eigenvalue. To do this, we solve the one-dimensional neutron diffusion equation for two energy groups, where the nuclear parameters are uniform in both nuclear fuel and reflector regions. The eigenvalue will be determined from the analytical solution using the power method iteratively until reaching convergence in both flux and eigenvalue. The results obtained in this paper are compared to those from numerical methods used to validate the proposed method. 2022 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280976035 en http://www.redalyc.org/revista.oa?id=7222 Brazilian Journal of Radiation Sciences application/pdf Sociedade Brasileira de Proteção Radiológica - SBPR Brazilian Journal of Radiation Sciences (Brasil) Num.3A Vol.10 |
| format | Artículo científico |
| id | redalyc_722280976035 |
| institution | Redalyc |
| language | en |
| publishDate | 2022 |
| publisher | Sociedade Brasileira de Proteção Radiológica - SBPR |
| spellingShingle | Analytical solution of the multigroup neutron diffusion equation coupled with an iterative method Adilson Costa da Silva Biología eigenvalue eigenvalue slab reactor slab reactor iterative method Analytical solution of the multigroup neutron diffusion equation coupled with an iterative method Adilson Costa da Silva Aquilino Senra Martinez Rodrigo Costa Diniz Alessandro da Cruz Gonçalves Biología eigenvalue eigenvalue slab reactor slab reactor iterative method Many numerical methods are being used to solve the multigroup neutron diffusion equation for different types of nuclear reactors. These methods solve this equation quite accurately and determine the neutron flux and power distribution in the reactor as well as the eigenvalue of the reactor core. In this paper, we are proposing the integration of an analytical solution with an iterative method to determine the neutron flux distribution in the reactor and the effective eigenvalue. To do this, we solve the one-dimensional neutron diffusion equation for two energy groups, where the nuclear parameters are uniform in both nuclear fuel and reflector regions. The eigenvalue will be determined from the analytical solution using the power method iteratively until reaching convergence in both flux and eigenvalue. The results obtained in this paper are compared to those from numerical methods used to validate the proposed method. 2022 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280976035 en http://www.redalyc.org/revista.oa?id=7222 Brazilian Journal of Radiation Sciences application/pdf Sociedade Brasileira de Proteção Radiológica - SBPR Brazilian Journal of Radiation Sciences (Brasil) Num.3A Vol.10 |
| title | Analytical solution of the multigroup neutron diffusion equation coupled with an iterative method |
| topic | Biología eigenvalue eigenvalue slab reactor slab reactor iterative method |
| url | https://www.redalyc.org/articulo.oa?id=722280976035 |