This paper presents an update on the development of an advanced methodology for core calculations that uses local heterogeneous solutions for on-the-fly nodal cross-section generation. The Iterative Transport-Diffusion Method is an embedded transport approach that is expected to provide results with near 3D transport accuracy for a fraction of the time required by a full 3D transport method. In this methodology, the infinite environment used for homogenized nodal cross-section generation is replaced with a simulated 3D environment of the diffusion calculation. This update focuses on burnup methodology, axial leakage and 3D modeling
International audiencePrevious burnup calculations of High Conversion Water Reactor (HCWR) options h...
Nodal diffusion codes have been successfully used for decades as a primary tool of commercial power ...
This project has resulted in a highly efficient method that has been shown to provide accurate solut...
The main objective of this research is to develop an integrated diffusion/transport (IDT) method to ...
This paper presents consistent and rigorous accuracy assessments of various methods for calculating ...
High conversion LWRs concepts typically rely on a heterogeneous core configuration, where fissile zo...
The current state of the art in reactor physics methods to assess safety, fuel failure, and operabil...
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 ...
This paper presents the accuracy assessments of various methods for calculating the diffusion coeffi...
Most modern nodal methods in use by the reactor vendors and utilities are based on the generalized e...
Diffusion approximation is an important approximation used to model a nuclear reactor core with a qu...
This thesis presents a systematic study on the merits and limitations on using pin-by-pin resolution...
The cores and reflectors of High Temperature Reactors (HTRs) of the Next Generation Nuclear Plant (N...
An innovative hybrid spatial discretization method is proposed to improve the computational efficien...
International audiencePrevious burnup calculations of High Conversion Water Reactor (HCWR) options h...
Nodal diffusion codes have been successfully used for decades as a primary tool of commercial power ...
This project has resulted in a highly efficient method that has been shown to provide accurate solut...
The main objective of this research is to develop an integrated diffusion/transport (IDT) method to ...
This paper presents consistent and rigorous accuracy assessments of various methods for calculating ...
High conversion LWRs concepts typically rely on a heterogeneous core configuration, where fissile zo...
The current state of the art in reactor physics methods to assess safety, fuel failure, and operabil...
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 ...
This paper presents the accuracy assessments of various methods for calculating the diffusion coeffi...
Most modern nodal methods in use by the reactor vendors and utilities are based on the generalized e...
Diffusion approximation is an important approximation used to model a nuclear reactor core with a qu...
This thesis presents a systematic study on the merits and limitations on using pin-by-pin resolution...
The cores and reflectors of High Temperature Reactors (HTRs) of the Next Generation Nuclear Plant (N...
An innovative hybrid spatial discretization method is proposed to improve the computational efficien...
International audiencePrevious burnup calculations of High Conversion Water Reactor (HCWR) options h...
Nodal diffusion codes have been successfully used for decades as a primary tool of commercial power ...
This project has resulted in a highly efficient method that has been shown to provide accurate solut...