Recent progress of the physics and engineering design study for the 8 m-sized DEMO is reported. Parametric study for the divertor of the compact DEMO (a machine size ∼ 5.5 m) by using the SONIC code shows that the target heat load less than 10 MW/m^2 around the fusion power of ∼1.5 GW and the impurity radiation fraction of more than 80 %. In the 8 m sized DEMO with these parameters, the partial detachment is obtained at the outer divertor, even in the low SOL density, due to the large impurity radiation in the SOL and divertor region. The SONIC simulation shows the peak of the target heat load is 7 MW/m^2. However, the peak of the ion temperature at the target is considerably high, which causes significant erosion of the target. The diverto...
Since 2014 preconceptual design activities for European DEMO divertor have been conducted as an inte...
Recent progress of Japan\u27s DEMO design is presented. The key concept is a steady-state DEMO with ...
© 2017 The Authors The main goal of the Divertor Tokamak Test facility (DTT) is to explore alternati...
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...
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 handling and the divertor design has been investigated in steady-state Japan DEMO concept of 1...
For a recent Japanese (JA) DEMO reactor design (Rp: 8 m size), the exhausted power to the SOL (Psep)...
Power handling in the divertor has been investigated for Japan DEMO concept. System code suggests th...
Power exhaust with impurity seeding scenario and the conceptual divertor design have been investigat...
An integrated divertor simulation code, SONIC, has been developed in order to predict a self-consist...
Power exhaust scenario and divertor design for a steady-state Japan (JA) DEMO and a pulse Europe (EU...
Power exhaust scenario for the feasible DEMO plasmas and the divertor design have been studied with ...
Power exhaust scenario and divertor design for a steady-state Japan (JA) DEMO and a pulse Europe (EU...
Since 2014 preconceptual design activities for European DEMO divertor have been conducted as an inte...
Recent progress of Japan\u27s DEMO design is presented. The key concept is a steady-state DEMO with ...
© 2017 The Authors The main goal of the Divertor Tokamak Test facility (DTT) is to explore alternati...
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...
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 handling and the divertor design has been investigated in steady-state Japan DEMO concept of 1...
For a recent Japanese (JA) DEMO reactor design (Rp: 8 m size), the exhausted power to the SOL (Psep)...
Power handling in the divertor has been investigated for Japan DEMO concept. System code suggests th...
Power exhaust with impurity seeding scenario and the conceptual divertor design have been investigat...
An integrated divertor simulation code, SONIC, has been developed in order to predict a self-consist...
Power exhaust scenario and divertor design for a steady-state Japan (JA) DEMO and a pulse Europe (EU...
Power exhaust scenario for the feasible DEMO plasmas and the divertor design have been studied with ...
Power exhaust scenario and divertor design for a steady-state Japan (JA) DEMO and a pulse Europe (EU...
Since 2014 preconceptual design activities for European DEMO divertor have been conducted as an inte...
Recent progress of Japan\u27s DEMO design is presented. The key concept is a steady-state DEMO with ...
© 2017 The Authors The main goal of the Divertor Tokamak Test facility (DTT) is to explore alternati...