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KIT-INR Contacts
Contact Reactor Technology, Fusion Technology, Renewable Energies, Energy Conversion
Sem_Serikov_18_05_2026 - inr.kit.edu
This seminar talk presents the most significant results from my six years of experience in neutronics analyses conducted at the KIT-INR Neutronics and Nuclear Data (NK) group. These analyses were performed in support of the design development for IFMIF-DONES (International Fusion Materials Irradiation Facility – DEMO Oriented Neutron Source). Of particular importance are the nuclear safety ...
KIT-INR Teams - Measurement Technology and Experimental Methods ...
Overview of CAD designs of the IFMIF Target and Test cell and the High Flux Test Module, designed at the Institute of Neutron physics and Reactor technology (INR) at KIT
KIT-INR Teams - Measurement Technology and Experimental Methods
Reactor Technology, Fusion Technology, Renewable Energies, Energy Conversion
KIT-INR Teams - Complex Experiments, Experimental Design - HELOKA
KIT has a long history in developing helium-cooled divertor solutions. The Helium-Multi-Jet (HEMJ) finger concept was the first that demonstrated experimentally that such a solution could withstand heat fluxes up to 14 MW/m². Following this tradition, under EUROfusion, the concept was developed further. Thus, instead of using the smaller 9-finger modules as previously proposed, the present ...
Thermal and Fluid Dynamic System Design - KIT
The code system SAS-SFR is the result of long-term cooperation between scientists from the KIT/INR (Germany), CEA, IRSN (France) and JAEA (Japan). The development started in the early eighties, taking the SAS4A code developed at ANL (USA) as a basis, but it became actually a new code frame due to a large number of improvements. Numerous coding errors and inconsistencies, found in the original ...
Analysis of Beyond Design Nuclear Events - KIT
The severe environment and the interaction with the neutron flux during the in-pile irradiation lead to a relevant variation of the nuclear fuel structure and characteristics. In order to properly estimate the status of the thermo-mechanical properties and dimensional variations of the fuel pins, several fuel performance codes have been developed and validated in the last decades. The ...
KIT-INR Teams - Neutronics and Nuclear Data - Nuclear Design Analyses
The main activities in the area of nuclear design analyses are devoted to studies on the development of fusion demonstration reactors and power plants, and specific neutronics tasks for the International Thermonuclear Experimental Reactor (ITER). The focus of these activities is on the design optimization of reactor components such as the blanket, the shield, the divertor, plasma heating and ...
KIT-INR Teams - Neutronics and Nuclear Data - Nuclear Data for Fusion ...
TALYS code with GDH model The geometry dependent hybrid model proposed by M.Blann and supplied with models for the non-equilibrium cluster emission was implemented in the TALYS code. Go to TALYS-G page ALICE/ASH code with modelling of heavy cluster emission (A > 4) Authors: M.Blann et al The ALICE/ASH code is an advanced and modified version of the ALICE code originated by M.Blann. The ...
Reaktorphysik und -dynamik - Design Basis Accidents - KIT
Reaktortechnologie, Fusionstechnologie, Erneuerbare Energien, Energiekonversion Methods and Codes for the Analysis of Design Basis Accidents
KIT-INR Teams - Thermal and Fluid Dynamic System Design - Thermal ...
Reactor Technology, Fusion Technology, Renewable Energies, Energy Conversion
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