summary:In this paper, the initial value problem for the equations of reactor kinetics is solved and the temperature feedback is taken into account. The space where the problem is solved is chosen in such a way that it may correspond best of all to the mathematical properties of the cross-section models. The local solution is found by the method of iterations, its uniqueness is proved and it is shown also that existence of global solution is ensured in the most cases. Finally, the problem of mild solution is discussed
AbstractThis work deals with a new technique for the numerical integration of the system of differen...
A general formulation of the kinetics equations of a system of coupled reactors is developed within ...
The paper describes a new numerical code for multigroup transient analyses with thermal feedback. Th...
summary:In this paper, the initial value problem for the equations of reactor kinetics is solved and...
summary:In this paper, the linear problem of reactor kinetics with delayed neutrons is studied whose...
summary:Using the qualitative theory of differential equations the equivalence of the boundary value...
Abstract: This work is devoted to the program complex for calculation of dynamic processes...
summary:The transport equation for the neutron density in an infinite absorbing and non-multiplying ...
The dynamic behavior of a fast reactor, when the neutron flux is considered as a function of time, i...
The numerical solution of the point kinetics equations in the presence of Newtonian temperature f...
The one-group diffusion theory of molten salt reactors in a homogeneous reactor model is revisited. ...
An analytical solution of the point kinetics equations to calculate reactivity as a funcion of time ...
AbstractThis article studies a system of reaction-diffusion equations describing neutron fission in ...
[[abstract]]A rigorous description of nuclear reactor kinetics usually invokes neutron transport the...
International audienceA rigorous simulation of industrial reactors in the case of solid-gas reacting...
AbstractThis work deals with a new technique for the numerical integration of the system of differen...
A general formulation of the kinetics equations of a system of coupled reactors is developed within ...
The paper describes a new numerical code for multigroup transient analyses with thermal feedback. Th...
summary:In this paper, the initial value problem for the equations of reactor kinetics is solved and...
summary:In this paper, the linear problem of reactor kinetics with delayed neutrons is studied whose...
summary:Using the qualitative theory of differential equations the equivalence of the boundary value...
Abstract: This work is devoted to the program complex for calculation of dynamic processes...
summary:The transport equation for the neutron density in an infinite absorbing and non-multiplying ...
The dynamic behavior of a fast reactor, when the neutron flux is considered as a function of time, i...
The numerical solution of the point kinetics equations in the presence of Newtonian temperature f...
The one-group diffusion theory of molten salt reactors in a homogeneous reactor model is revisited. ...
An analytical solution of the point kinetics equations to calculate reactivity as a funcion of time ...
AbstractThis article studies a system of reaction-diffusion equations describing neutron fission in ...
[[abstract]]A rigorous description of nuclear reactor kinetics usually invokes neutron transport the...
International audienceA rigorous simulation of industrial reactors in the case of solid-gas reacting...
AbstractThis work deals with a new technique for the numerical integration of the system of differen...
A general formulation of the kinetics equations of a system of coupled reactors is developed within ...
The paper describes a new numerical code for multigroup transient analyses with thermal feedback. Th...