This paper presents a new hybrid method of continuous energy Monte Carlo (MC) and multi-group Method of Characteristics (MOC). For a continuous energy neutron transport analysis, the hybrid method employs a continuous energy MC for resonance energy range to treat the resonances accurately and a multi-group MOC for high and low energy ranges for efficiency. Numerical test with a model problem confirms that the hybrid method can produce consistent results with the reference continuous energy MC-only calculation as well as multi-group MOC-only calculation
The continuous energy coarse mesh transport (COMET) method is a hybrid stochasticdeterministic solve...
We present the S 1 method, a hybrid neutron transport method in which Monte Carlo particles tra-vers...
The authors present the S{sub {infinity}} method, a hybrid neutron transport method in which Monte C...
This paper investigates mixing multi-group (MG) and continuous energy (CE) representation of cross-s...
This paper presents the application and evaluation of a deterministic truncation of Monte Carlo (DTM...
The neutron transport equation is solved by a hybrid method that iteratively couples regions where d...
A new hybrid neutron transport method was developed and implemented using the response matrix formul...
This thesis investigates the feasibility of Monte Carlo (MC) neutronic calculations that combine mul...
The accurate modeling of nuclear reactors is essential to the safe and economic operation of current...
Several new hybrid Monte Carlo-deterministic methods based on nonlinear functionals are developed in...
A new deterministic-Monte Carlo hybrid solution technique is derived for the time-dependent transpor...
In this work we investigate replacing standard quadrature techniques used in deterministic linear so...
In this paper, the modified power method originally introduced by Booth for one-dimensional one-grou...
This paper investigates the feasibility of performing reactor physics calculations using a hybrid ne...
All in-text references underlined in blue are linked to publications on ResearchGate, letting you ac...
The continuous energy coarse mesh transport (COMET) method is a hybrid stochasticdeterministic solve...
We present the S 1 method, a hybrid neutron transport method in which Monte Carlo particles tra-vers...
The authors present the S{sub {infinity}} method, a hybrid neutron transport method in which Monte C...
This paper investigates mixing multi-group (MG) and continuous energy (CE) representation of cross-s...
This paper presents the application and evaluation of a deterministic truncation of Monte Carlo (DTM...
The neutron transport equation is solved by a hybrid method that iteratively couples regions where d...
A new hybrid neutron transport method was developed and implemented using the response matrix formul...
This thesis investigates the feasibility of Monte Carlo (MC) neutronic calculations that combine mul...
The accurate modeling of nuclear reactors is essential to the safe and economic operation of current...
Several new hybrid Monte Carlo-deterministic methods based on nonlinear functionals are developed in...
A new deterministic-Monte Carlo hybrid solution technique is derived for the time-dependent transpor...
In this work we investigate replacing standard quadrature techniques used in deterministic linear so...
In this paper, the modified power method originally introduced by Booth for one-dimensional one-grou...
This paper investigates the feasibility of performing reactor physics calculations using a hybrid ne...
All in-text references underlined in blue are linked to publications on ResearchGate, letting you ac...
The continuous energy coarse mesh transport (COMET) method is a hybrid stochasticdeterministic solve...
We present the S 1 method, a hybrid neutron transport method in which Monte Carlo particles tra-vers...
The authors present the S{sub {infinity}} method, a hybrid neutron transport method in which Monte C...