In a demonstration (DEMO) reactor, mitigation of the large heat load on the divertor target to the below material and engineering limits is a key requirement for operation. Systems modeling is used to design entire fusion power plants and, therefore, has to be able to appropriately capture the divertor challenge. Therefore, it is important to validate these models against comprehensive SOL-divertor simulation codes and experiments. A 1-D divertor model in PROCESS was investigated, compared to the results of 2-D SONIC simulation under the detachment condition. The comparison shows how the 1-D divertor model handles the power loss mechanisms from the outboard mid-plane to the outer divertor target for a DEMO-like condition. The results show g...
Erosion reduction of tungsten (W) divertor target is one of the most important research subjects for...
The effect of divertor closure and nitrogen on the detachment process has been studied by performing...
In the European strategy towards fusion power, a demonstration tokamak fusion reactor (DEMO) is fore...
An integrated divertor simulation code, SONIC, has been developed in order to predict a self-consist...
Power handling in the divertor has been investigated for Japan DEMO concept. System code suggests th...
Recent progress of the physics and engineering design study for the 8 m-sized DEMO is reported. Para...
The divertor plasma performance and the power handling are studied for 8 m class DEMO reactor with t...
Power exhaust to the divertor and the conceptual design have been investigated for a steady-state DE...
The standard Single Null (SN) divertor is currently expected to be installed in DEMO. However, a num...
Handling of a large thermal power exhausted from the confined plasma is one of the most important is...
Power handling and the divertor design has been investigated in steady-state Japan DEMO concept of 1...
Power exhaust scenario for the feasible DEMO plasmas and the divertor design have been studied with ...
Conventional divertor concepts for recent DEMOs (P_fus=1.5-2GW, R_p=7-9m) were summarized. Requireme...
Power exhaust scenario for the feasible DEMO plasmas and the divertor design have been studied with ...
For a recent Japanese (JA) DEMO reactor design (Rp: 8 m size), the exhausted power to the SOL (Psep)...
Erosion reduction of tungsten (W) divertor target is one of the most important research subjects for...
The effect of divertor closure and nitrogen on the detachment process has been studied by performing...
In the European strategy towards fusion power, a demonstration tokamak fusion reactor (DEMO) is fore...
An integrated divertor simulation code, SONIC, has been developed in order to predict a self-consist...
Power handling in the divertor has been investigated for Japan DEMO concept. System code suggests th...
Recent progress of the physics and engineering design study for the 8 m-sized DEMO is reported. Para...
The divertor plasma performance and the power handling are studied for 8 m class DEMO reactor with t...
Power exhaust to the divertor and the conceptual design have been investigated for a steady-state DE...
The standard Single Null (SN) divertor is currently expected to be installed in DEMO. However, a num...
Handling of a large thermal power exhausted from the confined plasma is one of the most important is...
Power handling and the divertor design has been investigated in steady-state Japan DEMO concept of 1...
Power exhaust scenario for the feasible DEMO plasmas and the divertor design have been studied with ...
Conventional divertor concepts for recent DEMOs (P_fus=1.5-2GW, R_p=7-9m) were summarized. Requireme...
Power exhaust scenario for the feasible DEMO plasmas and the divertor design have been studied with ...
For a recent Japanese (JA) DEMO reactor design (Rp: 8 m size), the exhausted power to the SOL (Psep)...
Erosion reduction of tungsten (W) divertor target is one of the most important research subjects for...
The effect of divertor closure and nitrogen on the detachment process has been studied by performing...
In the European strategy towards fusion power, a demonstration tokamak fusion reactor (DEMO) is fore...