Modern nuclear reactor safety codes require the ability to solve detailed coupled neutronic- thermal fluids problems. For larger cores, this implies fully coupled higher dimensionality spatial dynamics with appropriate feedback models that can provide enough resolution to accurately compute core heat generation and removal during steady and unsteady conditions. The reactor analysis code PRONGHORN is being coupled to RELAP-7 as a first step to extend RELAP’s current capabilities. This report details the mathematical models, the type of coupling, and the testing results from the integrated system. RELAP-7 is a MOOSE-based application that solves the continuity, momentum, and energy equations in 1-D for a compressible fluid. The pipe and joint...
The development of an innovative coupled neutronic/thermo-hydraulic tool is reported hereafter. The ...
A research activity started at the end of 80’s was substantiated within the context of the participa...
This paper gives an account of the development and validation of an up-to-date coupled neutronic/the...
Modern nuclear reactor safety codes require the ability to solve detailed coupled neutronicthermal f...
The document contains the simulation results of a steady state model PWR problem with the RELAP-7 co...
Coupled calculations are important for the simulation of nuclear power plants when there is a strong...
The USNRC version of the 3D neutron kinetics code, Purdue Advanced Reactor Core Simulator (PARCS), h...
Thanks to continuous progress in computer technology, it is now possible to perform best-estimate si...
This article gives an account of the development and validation of the PARCS/RELAP5 model of the Rin...
Many power utilities worldwide are applying for power uprates, i.e. for increasing the power output ...
Subchannel codes have been widely used for thermal-hydraulics analyses in nuclear reactors. This pap...
This paper deals with the development of a coupled PARCS/RELAP5 model of the Swedish Ringhals-3 pres...
A research activity started at the end of 80’s was substantiated within the context of the participa...
ABSTRACT The USNRC version of the 3D neutron kinetics code, Purdue Simulator (PARCS), has been coupl...
© 2018 Elsevier Ltd Best-estimate codes, which couple neutronic and thermal-hydraulic solvers, are m...
The development of an innovative coupled neutronic/thermo-hydraulic tool is reported hereafter. The ...
A research activity started at the end of 80’s was substantiated within the context of the participa...
This paper gives an account of the development and validation of an up-to-date coupled neutronic/the...
Modern nuclear reactor safety codes require the ability to solve detailed coupled neutronicthermal f...
The document contains the simulation results of a steady state model PWR problem with the RELAP-7 co...
Coupled calculations are important for the simulation of nuclear power plants when there is a strong...
The USNRC version of the 3D neutron kinetics code, Purdue Advanced Reactor Core Simulator (PARCS), h...
Thanks to continuous progress in computer technology, it is now possible to perform best-estimate si...
This article gives an account of the development and validation of the PARCS/RELAP5 model of the Rin...
Many power utilities worldwide are applying for power uprates, i.e. for increasing the power output ...
Subchannel codes have been widely used for thermal-hydraulics analyses in nuclear reactors. This pap...
This paper deals with the development of a coupled PARCS/RELAP5 model of the Swedish Ringhals-3 pres...
A research activity started at the end of 80’s was substantiated within the context of the participa...
ABSTRACT The USNRC version of the 3D neutron kinetics code, Purdue Simulator (PARCS), has been coupl...
© 2018 Elsevier Ltd Best-estimate codes, which couple neutronic and thermal-hydraulic solvers, are m...
The development of an innovative coupled neutronic/thermo-hydraulic tool is reported hereafter. The ...
A research activity started at the end of 80’s was substantiated within the context of the participa...
This paper gives an account of the development and validation of an up-to-date coupled neutronic/the...