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A forward equation for stochastic neutron transport

Annals of Nuclear Energy, 1994
Abstract A new formalism is developed for describing the stochastic neutron transport by the forward approach. This is used to derive a forward stochastic transport equation for this process. The first moment of this equation is the usual transport equation for the singlet density while higher moments yield equations for the doublet and higher ...
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Neutron transport equations with spin-orbit coupling

Journal of Mathematical Physics, 1973
An ab initio derivation of the transport equations is given for fast neutrons traversing a material having spin zero nuclei. The resulting set of equations agrees with the equations of Bell and Goad except for the treatment of the coherent terms. Application of the equations to asymmetric situations is suggested.
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Linearized BGK and neutron transport equations in finite domains

Transport Theory and Statistical Physics, 1981
Abstract A study is made of the integro-differential equation For ψ(μ)=π−½e−μ2 this equation arises in the linearized BGK model; for ψ(μ)=½c(|μ|≤1), ψ(μ)=0(|μ|>1) it describes neutron transport in a slab with isotropic scattering. With the help of the existing theory of convolution equations solutions of various boundary value problems are obtained ...
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Stable Difference Schemes for the Neutron Transport Equation

AIP Conference Proceedings, 2011
The initial boundary value problem for the neutron transport equation is considered. The first and second orders of accuracy difference schemes for the approximate solution of this problem are presented. In applications, the stability estimates for solutions of difference schemes for the approximate solution of the neutron transport equation are ...
Allaberen Ashyralyev   +5 more
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Tschebyscheff Polynomial Approximation Method of the Neutron-Transport Equation

Journal of Mathematical Physics, 1961
The Tschebyscheff polynomial approximation method of the neutron-transport equation is developed. The relations between the relaxation constants in this approximation and the positive roots of TN+1(μ)=0 are derived. Using these relations, the necessary condition for reactor criticality is discussed.
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Spectral element solutions for the PN neutron transport equations

Computers & Fluids, 2011
zbMATH Open Web Interface contents unavailable due to conflicting licenses.
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A collocation method for the neutron transport equation

Transport Theory and Statistical Physics, 1983
Abstract One of the dominant numerical approximation methods for the integro-differential equation for neutron transport is the discrete-ordinates method1. In this method one collocates the equation at preselected angular directions which are the quadrature points of the integral scattering term (the “discrete ordinates”), and then solves the resulting
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Methods of solving neutron transport equation

2021
Anurag Gupta, Suhail Ahmad Khan
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New Difference Schemes for the Neutron Transport Equation

Nuclear Science and Engineering, 1971
Three new difference schemes for solving the neutron transport equation are presented. In some situations these new methods give smoother results than the diamond difference scheme, without sacrifi...
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