KIT - Karlsruhe Institute of Technology image/svg+xml
Institute for Neutron Physics and Reactor Technology
  • skip navigation
  • Home
  • Legals
  • Privacy Policy
  • Accessibility
  • Sitemap
  • KIT
  • de
search
  • At a glance
  • Contacts
  • Teams
    • Teams
    Teams
    • Analysis of Beyond Design Nuclear Events
      • Analysis of Beyond Design Nuclear Events
      Analysis of Beyond Design Nuclear Events
      • Fuel Performance Codes
      • Multi Physics Codes
      • Partners ande Projects
      • Safety Analysis of ADS
    • Thermal and Fluid Dynamic System Design
      • Thermal and Fluid Dynamic System Design
      Thermal and Fluid Dynamic System Design
      • Fusion
      • Nuclear Safety
      • Thermal-Hydraulics
        • Thermal-Hydraulics
        Thermal-Hydraulics
        • Adaptiven Strömungsbeeinflussung
      • Thermal-Hydraulic Test Facilities
      • LIMCKA
    • Design and Analyses of nuclear Components
      • Design and Analyses of nuclear Components
      Design and Analyses of nuclear Components
      • Design and Analyses
      • Qualification of Fabrication Technologies
      • Numerical modelling and experimental validation
    • Finance, Human Resources & Infrastructure
    • Complex Experiments, Experimental Design
      • Complex Experiments, Experimental Design
      Complex Experiments, Experimental Design
      • HELOKA
    • Measurement Technology and Experimental Methods
      • Measurement Technology and Experimental Methods
      Measurement Technology and Experimental Methods
      • Experimental Facilities
      • Cooling Gas Chemistry
      • Magnet Safety
      • Minichannel Gas Cooling
      • Design of Irradiation Experiments
    • Neutronics and Nuclear Data
      • Neutronics and Nuclear Data
      Neutronics and Nuclear Data
      • Nuclear Data for Fusion Technology
        • Nuclear Data for Fusion Technology
        Nuclear Data for Fusion Technology
        • Simulation Codes
      • Neutronic Experiments and Computational Analyses
      • Methods and Computational Tools
      • Nuclear Design Analyses
      • Neutronics for IFMIF
      • TALYS-G code
    • Reactor Physics and Dynamic
      • Reactor Physics and Dynamic
      Reactor Physics and Dynamic
      • Core Thermal Hydraulics
      • Multiscale Methods
      • Core Physics
      • Multiphysics Methods
      • Design Basis Accidents
      • Severe Accidents
      • Uncertainty and Sensitivity
      • RPD Projects
    • Thermal-hydraulic Simulations and Optimization
  • Study
    • Study
    Study
    • Lectures
    • Seminar
    • Summer School
  • Theses & Jobs
  • In Memoriam
    • In Memoriam
    In Memoriam
    • Expression of Thanks
  • Startpage
  • Home
  • Legals
  • Privacy Policy
  • Accessibility
  • Sitemap
  • search
Institute for Neutron Physics and Reactor Technology

 

  • Startpage
  • Teams
  • Finance, Human Resources & Infrastructure

 

  • Startpage
    • At a glance
    • Contacts
    • Teams
    • Study
    • Theses & Jobs
    • In Memoriam
  • Teams
    • Analysis of Beyond Design Nuclear Events
    • Thermal and Fluid Dynamic System Design
    • Design and Analyses of nuclear Components
    • Finance, Human Resources & Infrastructure
    • Complex Experiments, Experimental Design
    • Measurement Technology and Experimental Methods
    • Neutronics and Nuclear Data
    • Reactor Physics and Dynamic
    • Thermal-hydraulic Simulations and Optimization
  • Finance, Human Resources & Infrastructure

Finance, Human Resources & Infrastructure

 

FPI Contact

Dr. R. Schwarz

rainer.schwarz∂kit.edu 

 

D. Tahir

dina tahir ∂does-not-exist.kit edu

Credits cover image: INR KIT last change: 2024-01-17
KIT – The Research University in the Helmholtz Association
  • Home
  • Legals
  • Privacy Policy
  • Accessibility
  • Sitemap
  • KIT