The theory of the pulsed neutron experiment and the 2 zone exponential experiment is developed in this thesis. The energy dependent diffusion approximation to the Boltzniann neutron transport equation is used throughout. A concise operator and vector foi^malism is introduced ii^ich permits a unified treatment of the variety of representations (multigroup, polynomial expansion, etc. ) of the diffusion equation. Familiarity with this formalism is developed by first considering the well understood eigenvalue theory of the asymptotic pulsed neutron experiment. New material is presented in Chapter 3 in that the theory of the pre-asymptotic pulsed neutron experiment given assumes a finite and not an instantaneous pulse. Part of the contents of th...
Owing to their inherent complexity, stochastic neutron transport problems are often examined by eith...
A simple model of time-independent neutron transport on a line as a stochastic process, using the me...
Abstract: Algorithms are obtained to compute spatial kinetics of nuclear reactor in diffus...
The theory of the pulsed neutron experiment and the 2 zone exponential experiment is developed in th...
For a measurement of the diffusion constant D from the decay of the fundamental mode only, optimal d...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
The space asymptotic theory has constituted a powerful tool for the determination of neutron energy ...
We apply to a simple example, taken from neutron thermalization, techniques we have been using in th...
The method of singular eigenfunctions introduced first by Van Kampen and developed later by Case and...
The Boltzmann transport equation describing the steady state distribution in energy of fast neutrons...
The time-dependent thermal neutron energy spectra, for times greater thsn the slowing-down time, wer...
Graduation date: 1983Describing functions have traditionally been used to obtain the\ud solutions of...
Space asymptotic theory is shown to be a suitable model for the study of pulsed experiments in neutr...
We develop a fully analytical study of the spectrum of the neutron diffusion operator both for spat...
six figuresThe Neutron Transport Equation (NTE) describes the flux of neutrons through inhomogeneous...
Owing to their inherent complexity, stochastic neutron transport problems are often examined by eith...
A simple model of time-independent neutron transport on a line as a stochastic process, using the me...
Abstract: Algorithms are obtained to compute spatial kinetics of nuclear reactor in diffus...
The theory of the pulsed neutron experiment and the 2 zone exponential experiment is developed in th...
For a measurement of the diffusion constant D from the decay of the fundamental mode only, optimal d...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
The space asymptotic theory has constituted a powerful tool for the determination of neutron energy ...
We apply to a simple example, taken from neutron thermalization, techniques we have been using in th...
The method of singular eigenfunctions introduced first by Van Kampen and developed later by Case and...
The Boltzmann transport equation describing the steady state distribution in energy of fast neutrons...
The time-dependent thermal neutron energy spectra, for times greater thsn the slowing-down time, wer...
Graduation date: 1983Describing functions have traditionally been used to obtain the\ud solutions of...
Space asymptotic theory is shown to be a suitable model for the study of pulsed experiments in neutr...
We develop a fully analytical study of the spectrum of the neutron diffusion operator both for spat...
six figuresThe Neutron Transport Equation (NTE) describes the flux of neutrons through inhomogeneous...
Owing to their inherent complexity, stochastic neutron transport problems are often examined by eith...
A simple model of time-independent neutron transport on a line as a stochastic process, using the me...
Abstract: Algorithms are obtained to compute spatial kinetics of nuclear reactor in diffus...