JT-60SA high-beta steady-state scenario at 2.3MA, 1.7T with 30 MW and 17 MW of NBI heating, respectively, and 7 MW of ECRH power has been investigated with the integrated suite of core / SOL / divertor codes JINTRAC. Various fuelling rates/locations were investigated and it was found that high values of beta, and acceptable levels of power load on the divertor outer-target, can be achieved without impurity seeding for separatrix densities above 2 x 1019 m-3 and in conditions of partial divertor detachment. The 0D plasma parameters of the above reduced-power advanced scenario are discussed along with comparison against the reference values of the highest beta scenario in the JT-60SA research plan
To ensure optimal plasma performance at high Q fus for the baseline scenario foreseen for ITER, the ...
The fusion performance of ELMy H-mode 50-50 deuterium-tritium (DT) plasmas with 50-50 DT NBI injecti...
JT-60SA, the largest tokamak that will operate before ITER, has been designed and built jointly by J...
JT-60SA high-beta steady-state scenario at 2.3MA, 1.7T with 17 MW of NBI heating and 7 MW of ECRH po...
The mission of the future tokamak device JT-60SA, currently under construction at Naka, is to produc...
The integrated modelling code TOPICS has been extended to include the core impurity transport, and a...
The integrated modeling code TOPICS has been extended to couple impurity transports in core and scra...
A key issue for steady-state tokamak operation is to determine the edge conditions that are compatib...
A key issue for steady-state tokamak operation is to determine the edge conditions that are compatib...
Plasmas and their operation scenarios have been predicted by using integrated modelling codes toward...
A large superconducting machine, JT-60SA has been constructed to provide major contributions to the ...
Transport modelling of plasmas with internal transport barriers in JT-60U and JET tokamaks has been ...
To ensure optimal plasma performance at high Q fus for the baseline scenario foreseen for ITER, the ...
The fusion performance of ELMy H-mode 50-50 deuterium-tritium (DT) plasmas with 50-50 DT NBI injecti...
JT-60SA, the largest tokamak that will operate before ITER, has been designed and built jointly by J...
JT-60SA high-beta steady-state scenario at 2.3MA, 1.7T with 17 MW of NBI heating and 7 MW of ECRH po...
The mission of the future tokamak device JT-60SA, currently under construction at Naka, is to produc...
The integrated modelling code TOPICS has been extended to include the core impurity transport, and a...
The integrated modeling code TOPICS has been extended to couple impurity transports in core and scra...
A key issue for steady-state tokamak operation is to determine the edge conditions that are compatib...
A key issue for steady-state tokamak operation is to determine the edge conditions that are compatib...
Plasmas and their operation scenarios have been predicted by using integrated modelling codes toward...
A large superconducting machine, JT-60SA has been constructed to provide major contributions to the ...
Transport modelling of plasmas with internal transport barriers in JT-60U and JET tokamaks has been ...
To ensure optimal plasma performance at high Q fus for the baseline scenario foreseen for ITER, the ...
The fusion performance of ELMy H-mode 50-50 deuterium-tritium (DT) plasmas with 50-50 DT NBI injecti...
JT-60SA, the largest tokamak that will operate before ITER, has been designed and built jointly by J...