A new deterministic-Monte Carlo hybrid solution technique is derived for the time-dependent transport equation. This new approach is based on dividing the time domain into a number of coarse intervals and expanding the transport solution in a series of polynomials within each interval. The solutions within each interval can be represented in terms of arbitrary source terms by using precomputed response functions. In the current work, the time-dependent response function computations are performed using the Monte Carlo method, while the global time-step march is performed deterministically. This work extends previous work by coupling the time-dependent expansions to space- and angle-dependent expansions to fully characterize the 1D transport...
In this work we investigate replacing standard quadrature techniques used in deterministic linear so...
Three-dimensional, full core modeling with pin-resolved detail has become the state of the art in co...
A new hybrid neutron transport method was developed and implemented using the response matrix formul...
The neutron transport equation is solved by a hybrid method that iteratively couples regions where d...
We present the S 1 method, a hybrid neutron transport method in which Monte Carlo particles tra-vers...
Until recently, reactor transient problems were exclusively solved by approximate deterministic meth...
Several new hybrid Monte Carlo-deterministic methods based on nonlinear functionals are developed in...
Typescript (photocopy).High order numerical solutions of the time-dependent one speed neutron transp...
The authors present the S{sub {infinity}} method, a hybrid neutron transport method in which Monte C...
The finite element response matrix method has been applied to the solution of the neutron transport ...
International audienceTime-dependent Monte Carlo neutron transport is key to addressing several appl...
This research develops an improved methodology (and corresponding code) for solving the time-depende...
A numerical method is presented for solving the time-dependent survival probability equation in gene...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
This paper presents a new hybrid method of continuous energy Monte Carlo (MC) and multi-group Method...
In this work we investigate replacing standard quadrature techniques used in deterministic linear so...
Three-dimensional, full core modeling with pin-resolved detail has become the state of the art in co...
A new hybrid neutron transport method was developed and implemented using the response matrix formul...
The neutron transport equation is solved by a hybrid method that iteratively couples regions where d...
We present the S 1 method, a hybrid neutron transport method in which Monte Carlo particles tra-vers...
Until recently, reactor transient problems were exclusively solved by approximate deterministic meth...
Several new hybrid Monte Carlo-deterministic methods based on nonlinear functionals are developed in...
Typescript (photocopy).High order numerical solutions of the time-dependent one speed neutron transp...
The authors present the S{sub {infinity}} method, a hybrid neutron transport method in which Monte C...
The finite element response matrix method has been applied to the solution of the neutron transport ...
International audienceTime-dependent Monte Carlo neutron transport is key to addressing several appl...
This research develops an improved methodology (and corresponding code) for solving the time-depende...
A numerical method is presented for solving the time-dependent survival probability equation in gene...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
This paper presents a new hybrid method of continuous energy Monte Carlo (MC) and multi-group Method...
In this work we investigate replacing standard quadrature techniques used in deterministic linear so...
Three-dimensional, full core modeling with pin-resolved detail has become the state of the art in co...
A new hybrid neutron transport method was developed and implemented using the response matrix formul...