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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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Analysis of Beyond Design Nuclear Events
Analysis of Beyond Design Nuclear Events
Fuel Performance Codes
Multi Physics Codes
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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
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Thermal and Fluid Dynamic System Design
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Thermal-Hydraulic Test Facilities
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Design and Analyses of nuclear Components
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Design and Analyses of nuclear Components
Design and Analyses of nuclear Components
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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
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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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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
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Design Basis Accidents
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Thermal-hydraulic Simulations and Optimization
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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
Download TALYS-G
TALYS-1.95 G (beta)
TALYS-1.7 G
last changes: June 2018
TALYS-1.0 G
last changes: October 2010