KIT - Karlsruhe Institute of Technology
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Institute for Neutron Physics and Reactor Technology
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Analysis of Beyond Design Nuclear Events
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Teams
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
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Thermal and Fluid Dynamic System Design
Thermal and Fluid Dynamic System Design
Fusion
Nuclear Safety
Thermal-Hydraulics
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Thermal and Fluid Dynamic System Design
Thermal-Hydraulics
Thermal-Hydraulics
Adaptiven Strömungsbeeinflussung
Thermal-Hydraulic Test Facilities
LIMCKA
Design and Analyses of nuclear Components
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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
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Complex Experiments, Experimental Design
Complex Experiments, Experimental Design
HELOKA
Measurement Technology and Experimental Methods
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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
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Neutronics and Nuclear Data
Neutronics and Nuclear Data
Nuclear Data for Fusion Technology
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Teams
Neutronics and Nuclear Data
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
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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
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Home
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Institute for Neutron Physics and Reactor Technology
Startpage
Teams
Neutronics and Nuclear Data
TALYS-G code
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
Neutronics and Nuclear Data
Nuclear Data for Fusion Technology
Neutronic Experiments and Computational Analyses
Methods and Computational Tools
Nuclear Design Analyses
Neutronics for IFMIF
TALYS-G code
TALYS-G code
Developers and contributors
A.J. Koning
M. Blann
J. Bisplinghoff
C.H.M. Broeders
A.I. Dityuk
U. Fischer
A.Yu. Konob
eyev
Yu.A. Korovin
D. Leichtle
V.P. Lunev
P.E. Pereslavtsev
Yu.N. Shubin
H.K. Vonach
