The predictor-corrector quasi-static method (PCQM) is used to solve the transient problem in the STREAM code, a steady-state and transient reactor analysis code with the method of characteristics. In PCQM, the angular neutron flux undergoes a factorized split to form the product of shape and amplitude functions. The time-dependent neutron transport equation is solved to obtain the shape function whereas the amplitude function is obtained by resolving the exact point kinetics equations (EPKEs). A two-level coarse mesh finite difference technique is implemented to reduce the transient running time of the transport solution. Moreover, high-order polynomial interpolation is applied to the kinetics parameters utilized in EPKEs to reduce the erro...
Both the static and transient analysis of tightly coupled reactors differ from those of the loosely ...
In this paper, a new method that can be used for checking the proper implementation of time- or freq...
Transient calculation is one of the key parts in reactor safety analysis and system simulation. With...
The Advanced Multilevel Predictor-Corrector Quasi-static Method (AML-PCQM) is proposed in this work....
The present work represents a little but valuable contribution to the advancement of the research in...
The quasi-static method is a standard tool for the space-time solution of neutron transport problems...
Several methods have recently been developed to solve multiphysics transients using the Improved Qua...
Three-dimensional, full core modeling with pin-resolved detail has become the state of the art in co...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
International audienceThe quasi-static method is widely used for space- and time-dependent neutron t...
A deterministic method for solving the time-dependent, three-dimensional Boltzmam transport equation...
The stiffness confinement method (SCM) is frequently employed to solve the reactor dynamics equation...
SIMMER is a coupled (neutronics, thermal-hydraulics, structure) code for nuclear reactor safety stud...
In the state of the art of computer technology, the transient analysis in the nuclear reactor has be...
Of the methods available by which to integrate the neutron and delayed neutron precursor balance equ...
Both the static and transient analysis of tightly coupled reactors differ from those of the loosely ...
In this paper, a new method that can be used for checking the proper implementation of time- or freq...
Transient calculation is one of the key parts in reactor safety analysis and system simulation. With...
The Advanced Multilevel Predictor-Corrector Quasi-static Method (AML-PCQM) is proposed in this work....
The present work represents a little but valuable contribution to the advancement of the research in...
The quasi-static method is a standard tool for the space-time solution of neutron transport problems...
Several methods have recently been developed to solve multiphysics transients using the Improved Qua...
Three-dimensional, full core modeling with pin-resolved detail has become the state of the art in co...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
International audienceThe quasi-static method is widely used for space- and time-dependent neutron t...
A deterministic method for solving the time-dependent, three-dimensional Boltzmam transport equation...
The stiffness confinement method (SCM) is frequently employed to solve the reactor dynamics equation...
SIMMER is a coupled (neutronics, thermal-hydraulics, structure) code for nuclear reactor safety stud...
In the state of the art of computer technology, the transient analysis in the nuclear reactor has be...
Of the methods available by which to integrate the neutron and delayed neutron precursor balance equ...
Both the static and transient analysis of tightly coupled reactors differ from those of the loosely ...
In this paper, a new method that can be used for checking the proper implementation of time- or freq...
Transient calculation is one of the key parts in reactor safety analysis and system simulation. With...