A generic semi-implicit coupling methodology has been developed and implemented in the RELAP5-3D © computer program. This methodology allows RELAP5-3D © to be used with other computer programs to perform integrated analyses of nuclear power reactor systems and related experimental facilities. The coupling methodology potentially allows different programs to be used to model different portions of the system. The programs are chosen based on their capability to model the phenomena that are important in the simulation in the various portions of the system being considered and may use different numbers of conservation equations to model fluid flow in their respective solution domains. The methodology was demonstrated using a test case in which ...
Modeling and numerical simulation of transient thermal-hydraulic phenomena in pool-type systems, suc...
The USNRC version of the 3D neutron kinetics code, Purdue Advanced Reactor Core Simulator (PARCS), h...
The objective of this work is to introduce an improvement in best estimate coupled neutronicthermalh...
An integrated code system consisting of RELAP5-3D and a multiphase CFD program has been created thro...
The three-field COBRA-TF subchannel analysis program has been incorporated in an integrated code sys...
Thesis (M.Ing. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2008.The Pebble ...
A mass and energy conserving form of explicit coupling has been developed for use with the RELAP5-3D...
Understanding and optimizing the relation between nuclear reactor components or physical phenomena a...
Modern nuclear reactor safety codes require the ability to solve detailed coupled neutronic- thermal...
The RELAP5-3D computer program has been improved with regard to its nearly-implicit numerical scheme...
At present, most of the widely used system codes for nuclear safety analysis are one-dimensional, wh...
7 pagesInternational audienceCEA, ANDRA and EDF are jointly developing the software platform ALLIANC...
Traditionally, the complex coupled physical phenomena in nuclear reactors has resulted in them being...
The present thesis describes the coupling of a three-dimensional continuous-energy Monte Carlo react...
This work describes the coupling methodology between a modified version of RELAP5/Mod3.3 and ANSYS F...
Modeling and numerical simulation of transient thermal-hydraulic phenomena in pool-type systems, suc...
The USNRC version of the 3D neutron kinetics code, Purdue Advanced Reactor Core Simulator (PARCS), h...
The objective of this work is to introduce an improvement in best estimate coupled neutronicthermalh...
An integrated code system consisting of RELAP5-3D and a multiphase CFD program has been created thro...
The three-field COBRA-TF subchannel analysis program has been incorporated in an integrated code sys...
Thesis (M.Ing. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2008.The Pebble ...
A mass and energy conserving form of explicit coupling has been developed for use with the RELAP5-3D...
Understanding and optimizing the relation between nuclear reactor components or physical phenomena a...
Modern nuclear reactor safety codes require the ability to solve detailed coupled neutronic- thermal...
The RELAP5-3D computer program has been improved with regard to its nearly-implicit numerical scheme...
At present, most of the widely used system codes for nuclear safety analysis are one-dimensional, wh...
7 pagesInternational audienceCEA, ANDRA and EDF are jointly developing the software platform ALLIANC...
Traditionally, the complex coupled physical phenomena in nuclear reactors has resulted in them being...
The present thesis describes the coupling of a three-dimensional continuous-energy Monte Carlo react...
This work describes the coupling methodology between a modified version of RELAP5/Mod3.3 and ANSYS F...
Modeling and numerical simulation of transient thermal-hydraulic phenomena in pool-type systems, suc...
The USNRC version of the 3D neutron kinetics code, Purdue Advanced Reactor Core Simulator (PARCS), h...
The objective of this work is to introduce an improvement in best estimate coupled neutronicthermalh...