In this work we investigate replacing standard quadrature techniques used in deterministic linear solvers with a fixed-seed Quasi-Monte Carlo calculation to obtain more accurate and efficient solutions to the neutron transport equation (NTE). Quasi-Monte Carlo (QMC) is the use of low-discrepancy sequences to sample the phase space in place of pseudo-random number generators used by traditional Monte Carlo (MC). QMC techniques decrease the variance in the stochastic transport sweep and therefore increase the accuracy of the iterative method. Historically, QMC has largely been ignored by the particle transport community because it breaks the Markovian assumption needed to model scattering in analog MC particle simulations. However, by using i...
The generation of multigroup neutron cross sections is usually the first step in the solution of rea...
In Monte Carlo particle transport, it is important to change the variance of calculations of relativ...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
The Iterative Quasi-Monte Carlo method, or iQMC, replaces standard quadrature techniques used in det...
This paper examines the use of quasirandom sequences of points in place of pseudorandom points in Mo...
The neutron transport equation is solved by a hybrid method that iteratively couples regions where d...
This thesis investigates the feasibility of Monte Carlo (MC) neutronic calculations that combine mul...
The application of the Generalized Minimal Residual Method (GMRES) with right preconditioning is exa...
Several new hybrid Monte Carlo-deterministic methods based on nonlinear functionals are developed in...
<p>Today’s “grand challenge” neutron transport problems require 3-D meshes with billions of cells,<b...
International audienceA new Monte Carlo algorithm which solves transport equations of the neutron no...
A new deterministic-Monte Carlo hybrid solution technique is derived for the time-dependent transpor...
We present the S 1 method, a hybrid neutron transport method in which Monte Carlo particles tra-vers...
International audienceSolving the adjoint linear transport equation by Monte Carlo methods can be co...
The theoretical treatment of the transport of particles and radiation gives rise to problems of grea...
The generation of multigroup neutron cross sections is usually the first step in the solution of rea...
In Monte Carlo particle transport, it is important to change the variance of calculations of relativ...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
The Iterative Quasi-Monte Carlo method, or iQMC, replaces standard quadrature techniques used in det...
This paper examines the use of quasirandom sequences of points in place of pseudorandom points in Mo...
The neutron transport equation is solved by a hybrid method that iteratively couples regions where d...
This thesis investigates the feasibility of Monte Carlo (MC) neutronic calculations that combine mul...
The application of the Generalized Minimal Residual Method (GMRES) with right preconditioning is exa...
Several new hybrid Monte Carlo-deterministic methods based on nonlinear functionals are developed in...
<p>Today’s “grand challenge” neutron transport problems require 3-D meshes with billions of cells,<b...
International audienceA new Monte Carlo algorithm which solves transport equations of the neutron no...
A new deterministic-Monte Carlo hybrid solution technique is derived for the time-dependent transpor...
We present the S 1 method, a hybrid neutron transport method in which Monte Carlo particles tra-vers...
International audienceSolving the adjoint linear transport equation by Monte Carlo methods can be co...
The theoretical treatment of the transport of particles and radiation gives rise to problems of grea...
The generation of multigroup neutron cross sections is usually the first step in the solution of rea...
In Monte Carlo particle transport, it is important to change the variance of calculations of relativ...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...