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In this contribution, we will use the Maxwell-Cartesian spherical harmonics (introduced in [1,2]) to derive a system of partial differential equations governing transport of neutrons within an interacting medium. This system forms an alternative to the well known approximation, which is based on the expansion of the directional dependence into tesseral spherical harmonics ([3,p.197]). In comparison with this latter set of equations, the Maxwell-Cartesian system posesses a much more regular structure,...
We present an iterative method based on an infinite dimensional adaptation of the
successive overrelaxation (SOR) algorithm for solving the 2-D neutron transport equation.
In a wide range of application, the neutron transport operator admits a Self-Adjoint and
m-Accretive Splitting (SAS). This splitting leads to an ADI-like iterative method which
converges unconditionally and is equivalent to a fixed point problem where the operator is
a 2 by 2 matrix...
In this paper, we study the homogenization and localization of a spectral transport equation posed in a locally periodic heterogeneous domain. This equation models the equilibrium of particles interacting with an underlying medium in the presence of a creation mechanism such as, for instance, neutrons in nuclear reactors. The physical coefficients of the domain are -periodic functions modulated by a macroscopic variable, where is a small parameter. The mean free path of the particles is also...
In this paper, we study the homogenization and localization of a
spectral transport equation posed in a locally periodic
heterogeneous domain. This equation models the equilibrium of
particles interacting with an underlying medium in the presence of a
creation mechanism such as, for instance, neutrons in nuclear
reactors. The physical coefficients of the domain are
ε-periodic functions modulated by a macroscopic variable, where
ε is a small parameter. The mean free path of the particles...
We address the homogenization of an eigenvalue problem for the neutron transport
equation
in a periodic heterogeneous domain, modeling the criticality study of nuclear
reactor cores.
We prove that the neutron flux, corresponding to the first and unique positive
eigenvector,
can be factorized in the product of two terms, up to a remainder which goes
strongly to zero
with the period. One term is the first eigenvector of the transport equation in the
periodicity cell. The other term is the...
In this paper, a new concept of the Reactivity Trace Curve (RTC) for reactor power control is presented. The concept is demonstrated for a reactor model with one group of delayed neutrons, where the reactivity trace curve is simply a closed form exponential solution of the RTC-differential equation identifier. An extended reactor model of multigroup (six groups) of delayed neutrons is discussed for power control using the RTC-method which is based on numerical solution of the governing equation...
The aim of this work is to introduce and to analyze new algorithms for solving the
transport neutronique equation in 2D geometry. These algorithms present the duplicate favors to be,
on the one hand faster than some classic algorithms and easily to be implemented and naturally
deviced for parallelisation on the other hand. They are based on a splitting of the collision operator
holding amount of caracteristics of the transport operator. Some numerical results are given at the end
of this work.
...
In this paper, we study the time asymptotic behavior of the solution to an abstract Cauchy problem on Banach spaces without restriction on the initial data. The abstract results are then applied to the study of the time asymptotic behavior of solutions of an one-dimensional transport equation with boundary conditions in -space arising in growing cell populations and originally introduced by M. Rotenberg, J. Theoret. Biol. 103 (1983), 181–199.
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