The main objective of this research is to develop an integrated diffusion/transport (IDT) method to substantially improve the accuracy of nodal diffusion methods for the design and analysis of Very High Temperature Reactors (VHTR). Because of the presence of control rods in the reflector regions in the Pebble Bed Reactor (PBR-VHTR), traditional nodal diffusion methods do not accurately model these regions, within which diffusion theory breaks down in the vicinity of high neutron absorption and steep flux gradients. The IDT method uses a local transport solver based on a new incident flux response expansion method in the controlled nodes. Diffusion theory is used in the rest of the core. This approach improves the accuracy of the core soluti...
SIGLEAvailable from TIB Hannover: RA 831(2573) / FIZ - Fachinformationszzentrum Karlsruhe / TIB - Te...
With a solution of the multigroup neutron transport equation available for a problem in one dimensio...
A new nodal method for the solution of multigroup multidimensional diffusion problems in hexagonal g...
The cores and reflectors of High Temperature Reactors (HTRs) of the Next Generation Nuclear Plant (N...
Today, the neutron-physical description of strong neutron absorbing materials for control and shut-d...
A new diffusion-transport hybrid nodal method in R-Z is presented that can effectively treat non-mul...
For the determination of control-rod efficiency in High Temperature Reactors with diffusion codes th...
OAK B202 Final Technical Report. The present generation of reactor analysis methods uses few-group n...
548 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1988.A family of highly efficient ...
Nodal diffusion codes have been successfully used for decades as a primary tool of commercial power ...
The superior advantage of a nodal method for reactor cores with hexagonal fuel assemblies discretize...
This project will develop a 3D, advanced coarse mesh transport method (COMET-Hex) for steady- state ...
Diffusion approximation is an important approximation used to model a nuclear reactor core with a qu...
summary:We present a method for solving the equations of neutron transport with discretized energeti...
This paper presents an update on the development of an advanced methodology for core calculations th...
SIGLEAvailable from TIB Hannover: RA 831(2573) / FIZ - Fachinformationszzentrum Karlsruhe / TIB - Te...
With a solution of the multigroup neutron transport equation available for a problem in one dimensio...
A new nodal method for the solution of multigroup multidimensional diffusion problems in hexagonal g...
The cores and reflectors of High Temperature Reactors (HTRs) of the Next Generation Nuclear Plant (N...
Today, the neutron-physical description of strong neutron absorbing materials for control and shut-d...
A new diffusion-transport hybrid nodal method in R-Z is presented that can effectively treat non-mul...
For the determination of control-rod efficiency in High Temperature Reactors with diffusion codes th...
OAK B202 Final Technical Report. The present generation of reactor analysis methods uses few-group n...
548 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1988.A family of highly efficient ...
Nodal diffusion codes have been successfully used for decades as a primary tool of commercial power ...
The superior advantage of a nodal method for reactor cores with hexagonal fuel assemblies discretize...
This project will develop a 3D, advanced coarse mesh transport method (COMET-Hex) for steady- state ...
Diffusion approximation is an important approximation used to model a nuclear reactor core with a qu...
summary:We present a method for solving the equations of neutron transport with discretized energeti...
This paper presents an update on the development of an advanced methodology for core calculations th...
SIGLEAvailable from TIB Hannover: RA 831(2573) / FIZ - Fachinformationszzentrum Karlsruhe / TIB - Te...
With a solution of the multigroup neutron transport equation available for a problem in one dimensio...
A new nodal method for the solution of multigroup multidimensional diffusion problems in hexagonal g...