Owing to their inherent complexity, stochastic neutron transport problems are often examined by either using highly simplified models to make solutions more accessible, or at the cost of significant computational effort for problems demanding higher accuracy than such simplified models afford. In this work, solutions to stochastic transport equations of varying complexity are developed to examine a particular quantity of interest, the neutron survival probability. Using these solutions, the behavior of the survival probability is characterized throughout a wide range of parameters to better inform expectations as the complexity of the problem is increased. First, the survival probability is modeled in an infinite medium. This provi...
In this paper, numerical methods aiming at determining the eigenfunctions, their adjoint and the cor...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
142 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1980.The solutions to various form...
The Neutron Transport Equation (NTE) describes the flux of neutrons over time through an inhomogeneo...
The neutron population in multiplying systems containing a weak random source departs significantly ...
A numerical method is presented for solving the time-dependent survival probability equation in gene...
six figuresThe Neutron Transport Equation (NTE) describes the flux of neutrons through inhomogeneous...
Methods of stochastic neutron transport are investigated and applied to novel formulations for the n...
International audienceReactor physics aims at studying the neutron population in a reactor core unde...
In this research the singular perturbation technique is used to solve the one-dimensional neutron tr...
The theory of the pulsed neutron experiment and the 2 zone exponential experiment is developed in th...
Time-dependent neutron transport in non-critical state can be expressed by the natural mode equation...
We give a stochastic representation of the principal eigenvalue of some homogeneous neutron transpor...
International audienceThe so-called Iterated Fission Probability (IFP) method has provided a major b...
This paper concerns numerical comparisons between five mathematical models capable of modelling the ...
In this paper, numerical methods aiming at determining the eigenfunctions, their adjoint and the cor...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
142 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1980.The solutions to various form...
The Neutron Transport Equation (NTE) describes the flux of neutrons over time through an inhomogeneo...
The neutron population in multiplying systems containing a weak random source departs significantly ...
A numerical method is presented for solving the time-dependent survival probability equation in gene...
six figuresThe Neutron Transport Equation (NTE) describes the flux of neutrons through inhomogeneous...
Methods of stochastic neutron transport are investigated and applied to novel formulations for the n...
International audienceReactor physics aims at studying the neutron population in a reactor core unde...
In this research the singular perturbation technique is used to solve the one-dimensional neutron tr...
The theory of the pulsed neutron experiment and the 2 zone exponential experiment is developed in th...
Time-dependent neutron transport in non-critical state can be expressed by the natural mode equation...
We give a stochastic representation of the principal eigenvalue of some homogeneous neutron transpor...
International audienceThe so-called Iterated Fission Probability (IFP) method has provided a major b...
This paper concerns numerical comparisons between five mathematical models capable of modelling the ...
In this paper, numerical methods aiming at determining the eigenfunctions, their adjoint and the cor...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
142 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1980.The solutions to various form...