A collision probability method has been developed for the modeling of nuclear reactor kinetics in one dimension in space and in time. The method is an integral transport method which is capable of solving general nuclear kinetics problems over an unlimited time interval and an infinite number of collision generations. The time dependent collision probability method is derived by first Laplace transforming the integro-differential form of the time dependent neutron transport equation. The resulting Laplace transformed equation involving a complex total cross section is then integrated by standard means to obtain the integral form of the neutron transport equation. The Laplace transform is then inverted to obtain an integral equation for t...
The accurate knowledge of the time-dependent spatial flux distribution in nuclear reactor is require...
Owing to their inherent complexity, stochastic neutron transport problems are often examined by eith...
Calculation of Pij matrix of one-dimensional neutron transport in the slab geometry of the nuclear f...
A collision probability method has been developed for the modeling of nuclear reactor kinetics in on...
A simplified stochastic model based on the forward stochastic model in the stochastic kinetics theor...
In a previous study, the stochastic space-dependent kinetics model (SSKM) based on the forward stoch...
[[abstract]]A rigorous description of nuclear reactor kinetics usually invokes neutron transport the...
With the rapid development of nuclear power industry, simulating and analyzing the reactor transient...
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...
textThe collision probability approach to neutron transport can be used to obtain the energy-depende...
A general formulation of the kinetics equations of a system of coupled reactors is developed within ...
summary:In this paper, the linear problem of reactor kinetics with delayed neutrons is studied whose...
SIMMER is a coupled (neutronics, thermal-hydraulics, structure) code for nuclear reactor safety stud...
The neutronics analysis of a fusion reactor is an important part of the overall system design. Howev...
The accurate knowledge of the time-dependent spatial flux distribution in nuclear reactor is require...
Owing to their inherent complexity, stochastic neutron transport problems are often examined by eith...
Calculation of Pij matrix of one-dimensional neutron transport in the slab geometry of the nuclear f...
A collision probability method has been developed for the modeling of nuclear reactor kinetics in on...
A simplified stochastic model based on the forward stochastic model in the stochastic kinetics theor...
In a previous study, the stochastic space-dependent kinetics model (SSKM) based on the forward stoch...
[[abstract]]A rigorous description of nuclear reactor kinetics usually invokes neutron transport the...
With the rapid development of nuclear power industry, simulating and analyzing the reactor transient...
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...
textThe collision probability approach to neutron transport can be used to obtain the energy-depende...
A general formulation of the kinetics equations of a system of coupled reactors is developed within ...
summary:In this paper, the linear problem of reactor kinetics with delayed neutrons is studied whose...
SIMMER is a coupled (neutronics, thermal-hydraulics, structure) code for nuclear reactor safety stud...
The neutronics analysis of a fusion reactor is an important part of the overall system design. Howev...
The accurate knowledge of the time-dependent spatial flux distribution in nuclear reactor is require...
Owing to their inherent complexity, stochastic neutron transport problems are often examined by eith...
Calculation of Pij matrix of one-dimensional neutron transport in the slab geometry of the nuclear f...