In reactor physics, the efficient solution of the multigroup neutron diffusion eigenvalue problem is desired for various applications. The diffusion problem is a lower-order but reasonably accurate approximation to the higher-fidelity multigroup neutron transport eigenvalue problem. In cases where the full-fidelity of the transport solution is needed, the solution of the diffusion problem can be used to accelerate the convergence of transport solvers via methods such as Coarse Mesh Finite Difference (CMFD). The diffusion problem can have O(108) unknowns, and, despite being orders of magnitude smaller than a typical transport problem, obtaining its solution is still not a trivial task. In the Michigan Parallel Characteristics Transport (MPAC...
Many applications in reactor physics still use the diffusion equation on a full reactor core with ho...
Thesis (Sc. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2005.Includes ...
Calculation of the neutron flux in a nuclear reactor core is ideally performed by solving the neutro...
In reactor physics, the efficient solution of the multigroup neutron diffusion eigenvalue problem is...
In this paper, we present a new multilevel in space and energy diffusion (MSED) method for solving m...
Nuclear engineers are interested in solutions of the Neutron Transport Equation (NTE), with the goal...
Time-dependent nuclear reactor simulations are essential in improving the safety, effectiveness, and...
This research explores the application of a reduced order modeling technique known as proper general...
The Coarse-Mesh Finite Difference (CMFD) method has been widely used to effectively accelerate neutr...
Method of characteristics (MOC) is one of the most efficient deterministic techniques for high fidel...
Ongoing efforts are being made to improve the performance of MPACT as the deterministic neutron tran...
Nuclear reactor design requires the calculation of integral core parameters and power and radiation ...
Several preconditioners based on multigroup di usion are developed for application to multiplying fi...
International audienceThe Laboratory for Reactor Physics and Systems Behaviour at the PSI and the EP...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
Many applications in reactor physics still use the diffusion equation on a full reactor core with ho...
Thesis (Sc. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2005.Includes ...
Calculation of the neutron flux in a nuclear reactor core is ideally performed by solving the neutro...
In reactor physics, the efficient solution of the multigroup neutron diffusion eigenvalue problem is...
In this paper, we present a new multilevel in space and energy diffusion (MSED) method for solving m...
Nuclear engineers are interested in solutions of the Neutron Transport Equation (NTE), with the goal...
Time-dependent nuclear reactor simulations are essential in improving the safety, effectiveness, and...
This research explores the application of a reduced order modeling technique known as proper general...
The Coarse-Mesh Finite Difference (CMFD) method has been widely used to effectively accelerate neutr...
Method of characteristics (MOC) is one of the most efficient deterministic techniques for high fidel...
Ongoing efforts are being made to improve the performance of MPACT as the deterministic neutron tran...
Nuclear reactor design requires the calculation of integral core parameters and power and radiation ...
Several preconditioners based on multigroup di usion are developed for application to multiplying fi...
International audienceThe Laboratory for Reactor Physics and Systems Behaviour at the PSI and the EP...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
Many applications in reactor physics still use the diffusion equation on a full reactor core with ho...
Thesis (Sc. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2005.Includes ...
Calculation of the neutron flux in a nuclear reactor core is ideally performed by solving the neutro...