Nuclear fusion is considered as a future source of sustainable energy supply. Since the H-mode discovery in ASDEX experiment "Divertor I" in 1982, the divertor has been an integral part of all modern tokamaks and stellarators. The major goal of this thesis is to develop a feasible divertor design for a fusion power plant to be built after ITER. The thesis describes the approach in the conceptual development of a helium-cooled divertor and the methods of verification and validation of the design
The International Thermonuclear Experimental Reactor (ITER) is a thermonuclear fusion experiment des...
Conventional divertor concepts for recent DEMOs (P_fus=1.5-2GW, R_p=7-9m) were summarized. Requireme...
Two significiant problems that need to be solved for any future fusion device are heat removal and p...
The thesis begins by describing the fusion process and operation of a fusion reactor, the approach i...
In a power plant scale fusion reactor, a huge amount of thermal power produced by the fusion reactio...
This report represents a summary of our knowledge after little more than one year of development of ...
The divertor target plates are the most thermally loaded in-vessel components in a fusion reactor wh...
In the European fusion roadmap, reliable power handling has been defined as one of the most critical...
Demonstrating the production of net electricity and operating with a closed fuel-cycle remain unargu...
Within the framework of the EU power plant conceptual study (PPCS), helium-cooled modular divertor c...
21siThe Eurofusion-DEMO design will complete the Pre Conceptual Design phase (PCD) with a PCD Gate, ...
Überblick über die thermohydraulischen Simulationsrechnungen zur Entwicklung eines heliumgeküh...
Controlled thermonuclear fusion opens up the possibility of using similar principles that take place...
Abstract As a demonstration fusion power plant, EU DEMO has to prove the maturity of fusion techno...
In the pursuit of realistically achievable design options for demonstrating fusion electricity gener...
The International Thermonuclear Experimental Reactor (ITER) is a thermonuclear fusion experiment des...
Conventional divertor concepts for recent DEMOs (P_fus=1.5-2GW, R_p=7-9m) were summarized. Requireme...
Two significiant problems that need to be solved for any future fusion device are heat removal and p...
The thesis begins by describing the fusion process and operation of a fusion reactor, the approach i...
In a power plant scale fusion reactor, a huge amount of thermal power produced by the fusion reactio...
This report represents a summary of our knowledge after little more than one year of development of ...
The divertor target plates are the most thermally loaded in-vessel components in a fusion reactor wh...
In the European fusion roadmap, reliable power handling has been defined as one of the most critical...
Demonstrating the production of net electricity and operating with a closed fuel-cycle remain unargu...
Within the framework of the EU power plant conceptual study (PPCS), helium-cooled modular divertor c...
21siThe Eurofusion-DEMO design will complete the Pre Conceptual Design phase (PCD) with a PCD Gate, ...
Überblick über die thermohydraulischen Simulationsrechnungen zur Entwicklung eines heliumgeküh...
Controlled thermonuclear fusion opens up the possibility of using similar principles that take place...
Abstract As a demonstration fusion power plant, EU DEMO has to prove the maturity of fusion techno...
In the pursuit of realistically achievable design options for demonstrating fusion electricity gener...
The International Thermonuclear Experimental Reactor (ITER) is a thermonuclear fusion experiment des...
Conventional divertor concepts for recent DEMOs (P_fus=1.5-2GW, R_p=7-9m) were summarized. Requireme...
Two significiant problems that need to be solved for any future fusion device are heat removal and p...