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Institute for Neutron Physics and Reactor Technology (INR)
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      • Core thermal hydraulic Analysis Methods
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        Core thermal hydraulic Analysis Methods
        • The subchannel thermal hydraulic code SubChanFlow
        • The Porous Media Two-phase Flow Code TwoPorFlow
      • Multiscale Methods for Reactor Safety
        • Multiscale Methods for Reactor Safety
        Multiscale Methods for Reactor Safety
        • Mutiscale Coupling of System Thermal Hydraulic with a Subchannel Codes
        • Multiscale Coupling of System Thermal Hydraulic with CFD-Codes
      • Core Neutronics Methods and Codes
        • Core Neutronics Methods and Codes
        Core Neutronics Methods and Codes
        • The finite element, parallel PN-transport solver based on domain-decomposition PARAFISH
        • PIRS Reactor Simulation Package
      • Multiphysics Methods for Improved Safety Evaluations of Reactor Systems
        • Multiphysics Methods for Improved Safety Evaluations of Reactor Systems
        Multiphysics Methods for Improved Safety Evaluations of Reactor Systems
        • Neutronic / Thermal Hydraulic/ Thermo-mechanics Coupled codes Based on Nodal Diffusion Solvers
        • Neutronic / Thermal Hydraulic Coupled codes Based on SP3-Transport Solvers
        • High fidelity Multiphysics based on Monte Carlo /SubChannel Codes
      • Methods and Codes for the Analysis of Design Basis Accidents
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Institute for Neutron Physics and Reactor Technology (INR)
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last change: 2008-05-09
KIT – The Research University in the Helmholtz Association
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