Three-dimensional, full core modeling with pin-resolved detail has become the state of the art in computational simulation for nuclear reactors. The primary objective of this dissertation is to develop a set of advanced algorithms to accurately and efficiently solve the time-dependent neutron transport equations with pin-resolved detail. The 2D/1D approach is used to reduce the computational burden of the direct 3D calculation of the neutron transport equation. The radial 2D solver utilizes the 2D Method of Characteristics (MOC) solution, and the 1D solver utilizes a 1D nodal solution. The 2D and 1D solutions are coupled using transverse leakages. In addition, a multi-group matrix (MGM) CMFD method is implemented, where the whole 3D matrix ...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
A second-order “Time-Dependent Multiple Balance” (TDMB) method for solving neutron transport problem...
Designing and analyzing nuclear reactors requires the development of software tools for the simulati...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
In the state of the art of computer technology, the transient analysis in the nuclear reactor has be...
The current state of the art in reactor physics methods to assess safety, fuel failure, and operabil...
A new approach based on the method of characteristics (MOC) is proposed to solve the neutron transpo...
A deterministic method for solving the time-dependent, three-dimensional Boltzmam transport equation...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
The factors introducing error in the solution of the Boltzmann transport equation, such as spatial d...
This paper presents a methodology developed and implemented in the neutron transport code STREAM to ...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
Abstract. We present an experimental study of two versions of a second-degree iterative method appli...
The Advanced Multilevel Predictor-Corrector Quasi-static Method (AML-PCQM) is proposed in this work....
In this paper we present a time-parallel algorithm for the 3D neutrons calculation of a transient mo...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
A second-order “Time-Dependent Multiple Balance” (TDMB) method for solving neutron transport problem...
Designing and analyzing nuclear reactors requires the development of software tools for the simulati...
Thesis: Ph. D. in Computational Nuclear Science and Engineering, Massachusetts Institute of Technolo...
In the state of the art of computer technology, the transient analysis in the nuclear reactor has be...
The current state of the art in reactor physics methods to assess safety, fuel failure, and operabil...
A new approach based on the method of characteristics (MOC) is proposed to solve the neutron transpo...
A deterministic method for solving the time-dependent, three-dimensional Boltzmam transport equation...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
The factors introducing error in the solution of the Boltzmann transport equation, such as spatial d...
This paper presents a methodology developed and implemented in the neutron transport code STREAM to ...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
Abstract. We present an experimental study of two versions of a second-degree iterative method appli...
The Advanced Multilevel Predictor-Corrector Quasi-static Method (AML-PCQM) is proposed in this work....
In this paper we present a time-parallel algorithm for the 3D neutrons calculation of a transient mo...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
A second-order “Time-Dependent Multiple Balance” (TDMB) method for solving neutron transport problem...
Designing and analyzing nuclear reactors requires the development of software tools for the simulati...