Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2014.Cataloged from PDF version of thesis.Includes bibliographical references (pages 195-200).Modeling full reactor cores with high fidelity transport methods is a difficult task, requiring the largest computers available today. This thesis presents work on an alternative approach using the eigenvalue response matrix method (ERMM). The basic idea of ERMM is to decompose a reactor spatially into local "nodes." Each node represents an independent fixed source transport problem, and the nodes are linked via approximate boundary conditions to reconstruct the global problem using potentially many fewer explicit unknowns than a direct fine mesh s...
A synthetically-accelerated response matrix method with heterogeneous coarse-mesh capability has bee...
International audienceIn this paper, we propose a new non-linear technique for accelerating the solu...
The overall objective of this thesis is to develop an economical computational method for multidimen...
This paper presents new algorithms for use in the eigenvalue response matrix method (ERMM) for react...
A new technique is developed with an alternative formulation of the response matrix method implement...
The finite element response matrix method has been applied to the solution of the neutron transport ...
A heterogeneous coarse mesh scheme based on the finite element response matrix has been developed an...
A response matrix method is applied to the time independent, mono-energetic transport equation. The ...
Master of ScienceDepartment of Mechanical and Nuclear EngineeringJeremy A. RobertsA novel approach b...
Three complementary methods have been implemented in the code Denovo that accelerate neutral particl...
Until recently, reactor transient problems were exclusively solved by approximate deterministic meth...
Presented is a stochastic-deterministic, response matrix method for transient analyses of nuclear sy...
In nuclear engineering, the λ -modes associated with the neutron diffusion equation are ...
The Monte Carlo response matrix method is used to solve computationally-intensive problems (e.g., la...
Stochastic Particle Response Calculator, SPaRC, is a new stochastic neutron transport code that has ...
A synthetically-accelerated response matrix method with heterogeneous coarse-mesh capability has bee...
International audienceIn this paper, we propose a new non-linear technique for accelerating the solu...
The overall objective of this thesis is to develop an economical computational method for multidimen...
This paper presents new algorithms for use in the eigenvalue response matrix method (ERMM) for react...
A new technique is developed with an alternative formulation of the response matrix method implement...
The finite element response matrix method has been applied to the solution of the neutron transport ...
A heterogeneous coarse mesh scheme based on the finite element response matrix has been developed an...
A response matrix method is applied to the time independent, mono-energetic transport equation. The ...
Master of ScienceDepartment of Mechanical and Nuclear EngineeringJeremy A. RobertsA novel approach b...
Three complementary methods have been implemented in the code Denovo that accelerate neutral particl...
Until recently, reactor transient problems were exclusively solved by approximate deterministic meth...
Presented is a stochastic-deterministic, response matrix method for transient analyses of nuclear sy...
In nuclear engineering, the λ -modes associated with the neutron diffusion equation are ...
The Monte Carlo response matrix method is used to solve computationally-intensive problems (e.g., la...
Stochastic Particle Response Calculator, SPaRC, is a new stochastic neutron transport code that has ...
A synthetically-accelerated response matrix method with heterogeneous coarse-mesh capability has bee...
International audienceIn this paper, we propose a new non-linear technique for accelerating the solu...
The overall objective of this thesis is to develop an economical computational method for multidimen...