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Plenary
Lecture
Abstract: The main problem in a reactor theory is to
find the neutrons distribution, hence its density. This
is the solution of an integral-differential equation
named the neutron transport equation and its knowledge
guaranties the safety and efficiently of the nuclear
reactor. This study deals with a topical problem of the
nuclear-physics: the solving of neutron transport
equation with variable coefficients. We shall use the
linearized version of the Boltzmann equation with the
numerous applications in physics, geophysics,
astrophysics, light scattering, radiative transfer of
stellar and planetary atmosphere. To solve the transport
equation we subdivide the overall domain into regions
within which the coefficients of equation (i.e. the
medium properties) are constant. A new homotopy
perturbation method is applied to obtain the continuous
solution of the integral-differential equation for a
multipoint boundary value problem. The idea of this
method consists in determining the series, whose sum
represents this solution. The speed of convergence of
the series is quite good, so only a few first terms
calculation ensures the satisfactory approximation of
the sought solution. A numerical example that confirms
the usefulness of the proposed algorithm for solving the
problems of this kind is also presented.
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