A general formulation of the kinetics equations of a system of coupled reactors is developed within the framework of neutron transport theory. The time behavior of the neutron population in a system of M interacting reactors is described by a set of M coupled generalized point kinetics equations. The kinetic behavior in each reactor being determined partly by its own characteristics and partly by the neutronic contribution from the rest of the system. The method of approach consists of describing the neutron population within a reactor by a single equation, the time dependent transport equation, and classifying neutrons on the surface of the reactor by groups according to the particular direction they travel with respect to a unit normal at...
SIMMER is a coupled (neutronics, thermal-hydraulics, structure) code for nuclear reactor safety stud...
This lecture describes the use of coupled 3D neutron kinetics and thermal hydraulics computer codes ...
[[abstract]]In a nuclear fission reactor, the decay constant of delayed neutrons will often determin...
A general formulation of the kinetics equations of a system of coupled reactors is developed within ...
[[abstract]]A rigorous description of nuclear reactor kinetics usually invokes neutron transport the...
The system of point kinetics equations describes the time behaviour of a nuclear reactor, as-suming ...
Typescript (photocopy).Analytic solutions of the multigroup space-time reactor kinetics equations ar...
AbstractThis work deals with a new technique for the numerical integration of the system of differen...
A two-group moderator response function method has been developed to analyze the dynamic characteris...
The dynamic behavior of a fast reactor, when the neutron flux is considered as a function of time, i...
>The Boltzmann equation for the neutron distribution in a reactor is discussed. Analytic and numeric...
In this paper, a new method that can be used for checking the proper implementation of time- or freq...
In Reference 1 (G.D. Spriggs, R.D. Busch, and John G. Williams, ``Two-Region Kinetic Model for Refle...
AbstractApplication of modified integral neutron kinetic model to calculate principal characteristic...
A mathematical model for study of the multi-core reactor system dynamics is formulated. This model c...
SIMMER is a coupled (neutronics, thermal-hydraulics, structure) code for nuclear reactor safety stud...
This lecture describes the use of coupled 3D neutron kinetics and thermal hydraulics computer codes ...
[[abstract]]In a nuclear fission reactor, the decay constant of delayed neutrons will often determin...
A general formulation of the kinetics equations of a system of coupled reactors is developed within ...
[[abstract]]A rigorous description of nuclear reactor kinetics usually invokes neutron transport the...
The system of point kinetics equations describes the time behaviour of a nuclear reactor, as-suming ...
Typescript (photocopy).Analytic solutions of the multigroup space-time reactor kinetics equations ar...
AbstractThis work deals with a new technique for the numerical integration of the system of differen...
A two-group moderator response function method has been developed to analyze the dynamic characteris...
The dynamic behavior of a fast reactor, when the neutron flux is considered as a function of time, i...
>The Boltzmann equation for the neutron distribution in a reactor is discussed. Analytic and numeric...
In this paper, a new method that can be used for checking the proper implementation of time- or freq...
In Reference 1 (G.D. Spriggs, R.D. Busch, and John G. Williams, ``Two-Region Kinetic Model for Refle...
AbstractApplication of modified integral neutron kinetic model to calculate principal characteristic...
A mathematical model for study of the multi-core reactor system dynamics is formulated. This model c...
SIMMER is a coupled (neutronics, thermal-hydraulics, structure) code for nuclear reactor safety stud...
This lecture describes the use of coupled 3D neutron kinetics and thermal hydraulics computer codes ...
[[abstract]]In a nuclear fission reactor, the decay constant of delayed neutrons will often determin...