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Marine Anderhuber

Research Engineer

Marine Anderhuber holds an engineering diploma (master's degree) in nuclear energy engineering from Grenoble INP (Phelma), France. She joined the French Alternative Energies and Atomic Energies Commission (CEA) in 2012. She works on the development and validation of the CATHARE thermal-hydraulics system code for sodium applications, in particular within boiling conditions. She contributed to the Generation IV ASTRID project, working on a new physical revision of CATHARE for sodium applications and validating the developments with the simulation of dedicated experiments. Currently, she is still working on the improvement of the code for Sodium Fast Reactor development, especially in the frame of coupling CATHARE with other codes (as the thermal-hydraulics code MATHYS, the neutronics code APOLLO3 and the thermomechanical code GERMINAL). She is also involved in CEA support of start-ups for the « new nuclear » selected in the call for projects « France 2030 innovative reactors ». Especially, she studies the thermohydraulics and neutronics coupling for Molten Salt Reactors simulations.​ Since 2019, she is also the quality representative and responsible for GUITHARE, the Graphical User Interface for CATHARE. She is at the interface between the GUI users, the CATHARE team and the GUI developers. In addition, she teaches nuclear reactor modeling with system code at the National Institute for Nuclear Science and Technology (INSTN).

 

  
  
  
VVUQ of a thermal-hydraulic multi-scale tool on unprotected loss of flow accident in SFR reactorEPJ Nuclear Sci. Technol. 7:3 2/5/2021
Some numerical achievements on Na boiling dynamics and next technical routeNuclear Engineering and Design,365:1107287/15/2020
Prospects for a CEA and ROSATOM/IPPE collaborative program on Na boiling for GEN IV SFRs safety rationale and thermal-hydraulic preparatory workProceedings of NURETH-18, USA8/18/2019
Validation of CATHARE 3 system code for sodium two phase flow application: R&D path and simulation of key test from the SIENA programProceedings of NURETH 17, China9/3/2017
Phenomenological Investigation of Sodium Boiling in a SFR Core during a postulated ULOF Transient with CATHARE 2 System Code: a Stabilized Boiling CaseJournal of Nuclear Science and Technology, 53, 692-69710/13/2015
Simulation of GR19 sodium boiling experiments with CATHARE 2 system code and Trio UúMC subchannel codeProceedings of NURETH 16, USA8/30/2015
Computational thermal hydraulic schemes for SFR transient studiesProceedings of NURETH 16, USA8/28/2015

 

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