Zobrazeno 1 - 10
of 25
pro vyhledávání: '"Claudio Zen Petersen"'
Autor:
Aquiles Almeida Ribeiro, Claudio Zen Petersen, Jorge Luiz de Mello Caurio Junior, Fernanda Tumelero
Publikováno v:
REMAT, Vol 10, Iss 2 (2024)
Neste trabalho, apresenta-se o método da exponencial de operadores, que consiste em uma técnica para resolver equações diferenciais parciais (EDPs) que envolvem operadores lineares com a característica de invariância. Partindo da ideia baseada
Externí odkaz:
https://doaj.org/article/3cfe857d3a14476c8f15716f24dc1752
Publikováno v:
Brazilian Journal of Radiation Sciences, Vol 12, Iss 2 (2024)
In this paper, a comparative analysis of numerical results of the neutron transport and diffusion theories for steady-state and transient multigroup problems is presented. The neutron transport equation is known as the one that best describes the beh
Externí odkaz:
https://doaj.org/article/0f9f4a1eeda34e0d94a360890d67e0d5
Publikováno v:
Brazilian Journal of Radiation Sciences, Vol 10, Iss 3 (2022)
In this paper, the solution of the Neutron Point Kinetics model is presented, adding the effects of temperature and absorbers poisons within a historical and technical context to simulate the preliminary characteristics of the Chernobyl accident. The
Externí odkaz:
https://doaj.org/article/6476250789774b45b010db41ce0103bc
Publikováno v:
Brazilian Journal of Radiation Sciences, Vol 10, Iss 1 (2022)
In this work, the Neutron Point Kinetics equations are solved for six groups of delayed neutron precursors and different types of ramp reactivity, considering the temperature effects by the Rosenbrock’s method, to verify the methodology. Furthermor
Externí odkaz:
https://doaj.org/article/ae105c3a24b04db6b7299c22c6769ec9
Publikováno v:
Brazilian Journal of Radiation Sciences, Vol 9, Iss 2A (2021)
In this work, we used a modified Picard’s method to solve the Multigroup Neutron Space Kinetics Equations (MNSKE) in Cartesian geometry. The method consists in assuming an initial guess for the neutron flux and using it to calculate a fictitious so
Externí odkaz:
https://doaj.org/article/c3e4f7cca2c847ef91d190a840faeb0b
Publikováno v:
Brazilian Journal of Radiation Sciences, Vol 8, Iss 3B (2021)
We describe in this work the application of the modified power method for solve the multigroup neutron diffusion eigenvalue problem in slab geometry considering two-dimensions for nuclear reactor global calculations. It is well known that criticality
Externí odkaz:
https://doaj.org/article/ef42faed39e8496eaec42e225f7a4ec1
Publikováno v:
REMAT, Vol 6, Iss 2 (2020)
Este trabalho apresenta uma análise comparativa entre algumas formas de aproximação das densidades de corrente em cálculos de criticalidade usando a teoria da difusão de nêutrons. Como os reatores nucleares são compostos por diversos materiais
Externí odkaz:
https://doaj.org/article/43d3db46e1a44b12b05c83b022a1a0dd
Autor:
Jaime Conte Zandoná, Natália Barros Schaun, Claudio Zen Petersen, Fernanda Tumelero, Marcelo Schramm
Publikováno v:
Brazilian Journal of Radiation Sciences, Vol 8, Iss 3 (2020)
Os autores apresentam uma abordagem semi-analítica para obter soluções para as equações da cinética pontual de nêutrons. A reatividade dependente do tempo é aproximada por aproximação constante por partes em tempo discretizado, e o sistema
Externí odkaz:
https://doaj.org/article/9d5f6ae9fb2743c5b3257c7e46771659
Publikováno v:
Brazilian Journal of Radiation Sciences. 10
In this paper, the solution of the Neutron Point Kinetics model is presented, adding the effects of temperature and absorbers poisons within a historical and technical context to simulate the preliminary characteristics of the Chernobyl accident. The
Publikováno v:
Brazilian Journal of Development. 6:19846-19858