Title of article :
Transport analysis of tungsten impurity in ITER
Author/Authors :
Murakami، نويسنده , , Y. and Amano، نويسنده , , T. and Shimizu، نويسنده , , K. and Shimada، نويسنده , , M.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2003
Abstract :
The radial distribution of tungsten impurity in ITER is calculated by using the 1.5D transport code TOTAL coupled with NCLASS, which can solve the neo-classical impurity flux considering arbitrary aspect ratio and collisionality. An impurity screening effect is observed when the density profile is flat and the line radiation power is smaller than in the case without impurity transport by a factor of 2. It is shown that 90 MW of line radiation power is possible without significant degradation of plasma performance (HH98(y,2)∼1) when the fusion power is 700 MW (fusion gain Q=10). The allowable tungsten density is about 7×1015/m3, which is 0.01% of the electron density and the increase of the effective ionic charge Zeff is about 0.39. In this case, the total radiation power is more than half of the total heating power 210 MW, and power to the divertor region is less than 100 MW. This operation regime gives an opportunity for high fusion power operation in ITER with acceptable divertor conditions. Simulations for the case with an internal transport barrier (ITB) are also performed and it is found that impurity shielding by an ITB is possible with density profile control.
Keywords :
NCLASS , impurity , transport , Tungsten , ITER
Journal title :
Journal of Nuclear Materials
Journal title :
Journal of Nuclear Materials