Integrated predictive modelling simulations of burning plasma experiment designs

Predictive simulations of ITER ͓R. Aymar et al., Plasma Phys. Control. Fusion 44, 519 ͑2002͔͒, discharges are carried out for the 15 MA high confinement mode ͑H-mode͒ scenario using PTRANSP, the predictive version of the TRANSP code. The thermal and toroidal momentum transport equations are evolved using turbulent and neoclassical transport models. A predictive model is used to compute the temperature and width of the H-mode pedestal. The ITER simulations are carried out for neutral beam injection ͑NBI͒ heated plasmas, for ion cyclotron resonant frequency ͑ICRF͒ heated plasmas, and for plasmas heated with a mix of NBI and ICRF. It is shown that neutral beam injection drives toroidal rotation that improves the confinement and fusion power production in ITER. The scaling of fusion power with respect to the input power and to the pedestal temperature is studied. It is observed that, in simulations carried out using the momentum transport diffusivity computed using the GLF23 model ͓R. Waltz et al., Phys. Plasmas 4, 2482 ͑1997͔͒, the fusion power increases with increasing injected beam power and central rotation frequency. It is found that the ITER target fusion power of 500 MW is produced with 20 MW of NBI power when the pedestal temperature is 3.5 keV.

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“…The MMM95 simulation results using PTRANSP are similar to corresponding BALDUR simulation results reported in Ref. 1.…”

Section: -5supporting

confidence: 83%

“…For instance, in Ref. 1, ITER simulations were carried out using the MMM95 transport model in the BALDUR code with prescribed auxiliary heating profiles, but with self-consistently evolving temperature, density, and current profiles. In Ref.…”

Section: Introductionmentioning

confidence: 99%

Predictive simulations of ITER including neutral beam driven toroidal rotation

et al. 2008

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“…Integrated modeling simulations included in previous studies 18,29 are repeated, with the addition of neoclassical tearing modes computed using the revised ISLAND module in order to study the impact of magnetic islands driven by NTMs on the plasma temperature profiles and total energy content.…”

Section: Magnetic Islands In Tokamak Simulationsmentioning

confidence: 99%

“…Simulations of a conventional H-mode discharge in ITER 18 were carried out using the same protocol that was used above in the simulations of JET and DIII-D. The results of ITER simulations that were carried out with no islands are compared with results of simulations with various combinations of islands, including a simulation of the ITER discharge with only the 3 / 2 island present; a simulation with only the 2 / 1 island present; a simulation in which the 3 / 2 and the 2 / 1 islands coexist; and a simulation in which the 3 / 2, the 2 / 1, and the 4 / 3 islands coexist.…”

Section: Effect Of the Magnetic Islands In Simulations Of Itermentioning

confidence: 99%

“…The discharges chosen include three normalized gyroradius scans, two ␤ scans, and a power scan. In addition, BALDUR simulations are carried out for an H-mode scenario in ITER 17,18 in order to investigate the adverse effects of tearing modes on the fusion burn. The adverse effects of magnetic islands in simulations of the JET, DIII-D, and ITER discharges are presented in Secs.…”

Section: Introductionmentioning

confidence: 99%

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Integrated simulations of saturated neoclassical tearing modes in DIII-D, Joint European Torus, and ITER plasmas

Halpern¹,

Bateman²,

Kritz³

2006

Physics of Plasmas

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tokamak discharges in order to investigate the adverse effects of multiple saturated magnetic islands driven by neoclassical tearing modes ͑NTMs͒. Simulations are carried out with a predictive model for the temperature and density pedestal at the edge of the high confinement mode ͑H-mode͒ plasma and with core transport described using the Multi-Mode model. The ISLAND module, which is used to compute magnetic island widths, includes the effects of an arbitrary aspect ratio and plasma cross sectional shape, the effect of the neoclassical bootstrap current, and the effect of the distortion in the shape of each magnetic island caused by the radial variation of the perturbed magnetic field. Radial transport is enhanced across the width of each magnetic island within the BALDUR integrated modeling simulations in order to produce a self-consistent local flattening of the plasma profiles. It is found that the main consequence of the NTM magnetic islands is a decrease in the central plasma temperature and total energy. For the DIII-D and JET discharges, it is found that inclusion of the NTMs typically results in a decrease in total energy of the order of 15%. In simulations of ITER, it is found that the saturated magnetic island widths normalized by the plasma minor radius, for the lowest order individual tearing modes, are approximately 24% for the 2 / 1 mode and 12% for the 3 / 2 mode. As a result, the ratio of ITER fusion power to heating power ͑fusion Q͒ is reduced from Q = 10.6 in simulations with no NTM islands to Q = 2.6 in simulations with fully saturated NTM islands.

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