Ignition Analysis on the High Field D-T Helical Reactor

Mitarai, O.; Sagara, A.; Sudo, S.; Motojima, O.

doi:10.13182/fst95-a11947087

Cited by 3 publications

(2 citation statements)

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“…The corresponding operation path to POPCON in figure 9 is shown in figure 10. The operation path is moved to the lower temperature and high density side by density increase when the fusion power starts to increase at 30 s. This is due to the fact that the density limit is increased by the increase in dW/dt at t = 31.45 s, because it is proportional to √ P NET = √ P L + dW/dt, as seen in equation (3). The difference between P EXT and dW/dt is P H = 20.2 MW, which is slightly larger than the height of the contour map and is used to overpass the saddle point.…”

Section: Ignition Access and The Heating Power With The Time Constant...mentioning

confidence: 99%

“…While system codes analysing the steady state plasma parameters have been used for stellarator reactors [1,2], we have been studying temporal evolutions of these parameters in helical reactors [3][4][5][6]. Recently, based on the Large Helical Device (LHD) ( ā = 0.6 m, B o = 3 T) experiments, we have determined the FFHR2m reactor size using the LHD size scaling including the blanket thickness and machine weight.…”

Section: Introductionmentioning

confidence: 99%

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Minimization of the external heating power by long fusion power rise-up time for self-ignition access in the helical reactor FFHR2m

et al. 2007

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Minimization of the external heating power to access self-ignition is advantageous to increase the reactor design flexibility and to reduce the capital and operating costs of the plasma heating device in a helical reactor. In this work we have discovered that a larger density limit leads to a smaller value of the required confinement enhancement factor, lower density limit margin reduces the external heating power, and over 300 s of the fusion power rise-up time makes it possible to reach a minimized heating power. While the fusion power rise-up time in a tokamak is limited by the OH transformer flux or the current drive capability, any fusion power rise-up time can be employed in a helical reactor for reducing the thermal stresses of the blanket and shields, because the confinement field is generated by the external helical coils.

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Section: Ignition Access and The Heating Power With The Time Constant...mentioning

confidence: 99%