The Georgia Institute of Technology (GA-Tech) recently developed a transport theory benchmark based closely on the geometry and the features of the HTTR reactor that is operational in Japan. Though simplified, the benchmark retains all the principal physical features of the reactor and thus provides a realistic and challenging test for the codes. The purpose of this paper is twofold. The first goal is an extension of the benchmark to diffusion theory applications by generating the additional data not provided in the GA-Tech prior work. The second goal is to use the benchmark on the HEXPEDITE code available to the INL. The HEXPEDITE code is a Green’s function-based neutron diffusion code in 3D hexagonal-z geometry. The results showed that th...
The general methodology be hind 2D arbitrary geometry neutron transport AGENT code is the theory of ...
An accurate and computationally efficient two or three-dimensional neutron diffusion model will be n...
This project will develop a 3D, advanced coarse mesh transport method (COMET-Hex) for steady- state ...
The cores and reflectors of High Temperature Reactors (HTRs) of the Next Generation Nuclear Plant (N...
Nodal diffusion codes have been successfully used for decades as a primary tool of commercial power ...
Both ECN and IRI take part in the benchmark of start-up core physics of the HighTemperature Engineer...
The main objective of this research is to develop an integrated diffusion/transport (IDT) method to ...
The Idaho National Laboratory (INL) is tasked with the development of reactor physics analysis capab...
The DIF3D code (DIFfusion 3D) has been a workhorse of fast reactor analysis work at Argonne National...
With a solution of the multigroup neutron transport equation available for a problem in one dimensio...
Temporary International Collective (TIC) was established in 1972 by an agreement among seven countri...
Diffusion approximation is an important approximation used to model a nuclear reactor core with a qu...
Today, the neutron-physical description of strong neutron absorbing materials for control and shut-d...
A new nodal method for the solution of multigroup multidimensional diffusion problems in hexagonal g...
The High Temperature engineering Test Reactor (HTTR) is an experimental High Temperature Gas-cooled ...
The general methodology be hind 2D arbitrary geometry neutron transport AGENT code is the theory of ...
An accurate and computationally efficient two or three-dimensional neutron diffusion model will be n...
This project will develop a 3D, advanced coarse mesh transport method (COMET-Hex) for steady- state ...
The cores and reflectors of High Temperature Reactors (HTRs) of the Next Generation Nuclear Plant (N...
Nodal diffusion codes have been successfully used for decades as a primary tool of commercial power ...
Both ECN and IRI take part in the benchmark of start-up core physics of the HighTemperature Engineer...
The main objective of this research is to develop an integrated diffusion/transport (IDT) method to ...
The Idaho National Laboratory (INL) is tasked with the development of reactor physics analysis capab...
The DIF3D code (DIFfusion 3D) has been a workhorse of fast reactor analysis work at Argonne National...
With a solution of the multigroup neutron transport equation available for a problem in one dimensio...
Temporary International Collective (TIC) was established in 1972 by an agreement among seven countri...
Diffusion approximation is an important approximation used to model a nuclear reactor core with a qu...
Today, the neutron-physical description of strong neutron absorbing materials for control and shut-d...
A new nodal method for the solution of multigroup multidimensional diffusion problems in hexagonal g...
The High Temperature engineering Test Reactor (HTTR) is an experimental High Temperature Gas-cooled ...
The general methodology be hind 2D arbitrary geometry neutron transport AGENT code is the theory of ...
An accurate and computationally efficient two or three-dimensional neutron diffusion model will be n...
This project will develop a 3D, advanced coarse mesh transport method (COMET-Hex) for steady- state ...