Physics basis for the fusion ignition research experiment plasma facing components

Ulrickson, M.; Brooks, J.N.; Hassenein, A.; Kessel, C.; Rognlien, T. D.; Wesley, J.C.; Meade, D. M.

doi:10.1016/s0920-3796(01)00227-7

Cited by 11 publications

(7 citation statements)

References 8 publications

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“…The triangularity is limited by the distance between the x-point and strike point on the inboard side to provide sufficient distance for power dissipation. Calculations indicate that the inboard should detach [4] over a wide range of parameters. The high triangularity provides higher ideal MHD beta limits, and leads to higher pedestal pressures [5][6][7] and access to higher plasma densities relative to the Greenwald density limit [7] with no energy confinement degradation.…”

Section: Physics Basis and Engineering Featuresmentioning

confidence: 99%

“…These pumps are backed up by turbo/drag pumps outside the biological shield. The predicted peak heat flux on the divertor ranges from 5 to 25 MW/m^2 [4], the lower values corresponding to detached and the higher to attached operation. The plasma facing surface in the divertor is tungsten bonded to a CuCrZr heat sink.…”

Section: Physics Basis and Engineering Featuresmentioning

confidence: 99%

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Physics basis and simulation of burning plasma physics for the fusion ignition research experiment (FIRE)

Kessel

Meade

Jardin

2002

Fusion Engineering and Design

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The FIRE design for a burning plasma experiment is described in terms of its physics basis and engineering features. Systems analysis indicates that the device has a wide operating space to accomplish its mission, both for the ELMing H-mode reference and the high bootstrap current/high β advanced tokamak regimes. Simulations with 1.5D transport codes reported here both confirm and constrain the systems projections. Experimental and theoretical results are used to establish the basis for successful burning plasma experiments in FIRE.

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Section: Physics Basis and Engineering Featuresmentioning

confidence: 99%

Section: Physics Basis and Engineering Featuresmentioning

confidence: 99%

Physics basis and simulation of burning plasma physics for the fusion ignition research experiment (FIRE)

Kessel

Meade

Jardin

2002

Fusion Engineering and Design

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“…Tungsten shows much promise as a plasma-facing material to use in magnetic fusion energy devices, both on the divertor and first-wall in tokamaks, and on plasma-forming electrodes in various advanced concepts [1][2][3][4][5][6]. Its refractory nature, moderate neutron activation properties, low retention of hydrogen isotopes and low sputter erosion rate are key features.…”

Section: Introductionmentioning

confidence: 99%

Recoil energy distribution of hydrogen isotopes adsorbed on tungsten

Bastasz

Whaley

2005

Journal of Nuclear Materials

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“…A key technological development is that of a focused, high-power, short-pulse neutral beam. An ~ 125 keV/amu beam at 1x10 6 Am -2 in a cross-section of 0.2 m x 0.2 m at the plasma edge for 1 µsec at 30 Hz repetition rate would be ideal. A high-speed repetitive impurity pellet injector should also be developed.…”

Section: Randd Requirementsmentioning

confidence: 99%

“…Section III addresses some issues of integration of diagnostics with the vacuum vessel, and its shielding and internal hardware. Section IV provides a short introduction to the status of alpha-particle diagnostic techniques, whose improvement is a major need in the Research and Development (R&D) needs described in section V. Descriptions of the FIRE mission and device can be found in reference [1] with details of the first-wall and plasma facing components described in reference [6].…”

Section: Introductionmentioning

confidence: 99%

Challenges for plasma diagnostics in a next step device (FIRE)

Young¹

Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231)

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Abstract--The physics program of any next step tokamak such as FIRE sets demands for plasma measurement which are at least as comprehensive as on present tokamaks, with the additional capabilities needed for control of the plasma and for understanding the effects of the alpha-particles. The diagnostic instrumentation must be able to provide the fine spatial and temporal resolution required for the advanced tokamak plasma scenarios. It must also be able to overcome the effects of neutron-and gamma-induced electrical noise in ceramic components or detectors, and fluorescence and absorption in optical components. There are practical engineering issues of minimizing radiation streaming while providing essential diagnostic access to the plasma. Many diagnostics will require components at or close to the first wall, e.g. ceramics and MI cable for magnetic diagnostics and mirrors for optical diagnostics; these components must be mounted to operate, and survive, in fluxes which require special material selection. A better set of diagnostics of alpha-particles than that available for TFTR is essential; it must be qualified well before moving into D-T experiments. A start has been made to assessing the potential implementation of key diagnostics for the FIRE device. The present status is described.

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Physics basis for the fusion ignition research experiment plasma facing components

Cited by 11 publications

References 8 publications

Physics basis and simulation of burning plasma physics for the fusion ignition research experiment (FIRE)

Physics basis and simulation of burning plasma physics for the fusion ignition research experiment (FIRE)

Recoil energy distribution of hydrogen isotopes adsorbed on tungsten

Challenges for plasma diagnostics in a next step device (FIRE)

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