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Neutron stochastic transport theory with delayed neutrons

Annals of Nuclear Energy, 1987
Abstract In this paper we have developed the stochastic transport theory with delayed neutrons. From this theory, the Boltzmann transport equation with delayed neutrons for the average flux emerges in a natural way without recourse to any approximation.
J.L. Muñoz-Cobo, G. Verdú
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Fixed Point Theory in MR-Metric Spaces Fundamental Theorems and Applications to Integral Equations and Neutron Transport

European Journal of Pure and Applied Mathematics
This paper establishes a comprehensive framework for fixed point theory in MR-metric spaces,a generalization of standard metric spaces that incorporates three-point relations.
T. Qawasmeh, Abed Al-Rahman M. Malkawi
semanticscholar   +1 more source

Neutron Transport Theory

1971
The general concept of “transport theory” refers to a physical process whereby a particle migrates through a lattice composed of scattering centers. The first important part of this concept is that the migrating material can be considered to be a particle, in the case of interest a neutron which changes its speed of travel as its total energy changes ...
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Neutron Transport: Theory, Modeling, and Computations

Graduate Texts in Physics, 2023
R. M. Kuridan
semanticscholar   +1 more source

Two-Group Perturbation Theory in Neutron Transport Theory

Proceedings of the Physical Society. Section A, 1954
This paper describes the application of perturbation theory to two-velocity-group neutron problems. We consider the exact integral equations satisfied by the neutron densities. The treatment is, therefore, not restricted to systems whose dimensions are large compared with the relevant mean free paths, and is more general than that reported by Glasstone
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Asymptotic Solutions in Neutron Transport Theory

Nuclear Science and Engineering, 1977
Asymptotic solutions, as obtained through the application of perturbation techniques to neutron transport theory, are constructed for different physical situations. In particular, large critical systems for both mono- and polyenergetic cases, as well as time-dependent problems, are considered. Numerical results are reported and discussed.
BOFFI V. C.   +2 more
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Functional methods in three-dimensional neutron transport theory

Meccanica, 1976
In this work, we are concerned with the stationary neutron transport Boltzmann equation (in its integral form) in a parallelepiped. Functional methods allow us to prove that the integral transport operator, which is defined in L2 space, has eigenvalues depending continuously and monotonically on geometrical and physical parameters.
BUSONI, GIORGIO   +2 more
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Unified Neutron Transport Theory

1979
I remember very well my first encounter with neutron transport theory. It was in 1948 or 1949 at Oak Ridge, where I was involved in critical mass calculations for a plant that performed chemical processing of uranium solutions. We had been using semi-empirical formulas provided for us by our consultant Richard Feynman, whose later accomplishments you ...
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Heavy Moderator Approximations in Neutron Transport Theory

Journal of Applied Physics, 1958
The flow of neutrons slowing down into a given angular and lethargy (or energy) interval equals an integral over the contributions from neutrons at other angles and lethargies within the medium. The two angular dependences of the integrand are commonly expanded in Legendre polynomials, and for heavy moderators, the lethargy dependence being integrated ...
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SPECTRAL APPROXIMATION THEORY FOR MULTIGROUP NEUTRON TRANSPORT OPERATORS

Acta Mathematica Scientia, 1986
Summary: By using operator theory in Banach space, we mainly study spectral approximation theory for the case of an inhomogeneous, anisotropically scattering, and arbitrarily finite convex body with any cavity in an L p context for general p, \(1\leq ...
Song, Yuhe, Yang, Mingzhu
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