Title :
COX-SIMU: A 3D Real Time Nodal Kinetic Code for the EDF EPR TREFLE Simulator
Author :
Akherraz, Bruno ; Kerkar, Nordine ; Mina, Pierre ; de Cordoue, Francois-Xavier ; Flores, Jean-Manuel ; Le-Roux, Charles ; Thierry, Philippe
Author_Institution :
Service d´Etudes et de Projets Thermiques Et Nucl. Electricite De France, Villeurbanne, France
Abstract :
The goal of the EDF TREFLE® project is to provide to the EPRTM project a full-scope simulator in order to perform design studies and operator training for the EPRTM reactor under construction at Flamanville, France. This article describes the 3D real time neutronic module, COX-SIMU, developed by EDF engineers and integrated in the simulator by the CORYS T.E.S.S Company. For the calculation of the 3D power distribution, COX-SIMU solves the neutron diffusion equations with 2 energy groups (transient and steady states). A full 3D distribution is needed due to the specifications of the EPRTM reactor internal instrumentation which requires knowledge of the detailed flux distribution for the Protection System. COX-SIMU includes thermal-hydraulical and thermal conduction modules to take into account the water moderator and fuel feedback on neutronic reactions. A simple model based on exponential functions is used for the calculation of the Residual Heat. COX-SIMU is fully validated against the industrial EDF neutronic code COCCINELLE with fine mesh discretization. The modularity and flexibility of COX-SIMU allow its integration in any Pressurized Water Reactor simulators. Thus, COX-SIMU is also integrated in the EPRTM TAISHAN Simulator.
Keywords :
digital simulation; fission reactors; neutron diffusion; nuclear engineering computing; power distribution; 3D power distribution; 3D real time neutronic module; 3D real time nodal kinetic code; COX-SIMU; EDF EPR TREFLE Simulator; EPRTM TAISHAN Simulator; EPRTM reactor; Flamanville; France; exponential functions; flux distribution; fuel feedback; full-scope simulator; industrial EDF neutronic code COCCINELLE; neutron diffusion equations; neutronic reactions; operator training; pressurized water reactor simulators; protection system; residual heat; steady state energy group; thermal conduction modules; thermal-hydraulical modules; transient energy group; water moderator; Equations; Fuels; Inductors; Mathematical model; Neutrons; Three-dimensional displays; Transient analysis; Nuclear Reactor; EPR; Neutronic; Real Time; Full Scope Simulator;
Conference_Titel :
Modelling and Simulation (EUROSIM), 2013 8th EUROSIM Congress on
Conference_Location :
Cardiff
DOI :
10.1109/EUROSIM.2013.118