A standard DT supershot simulation

Budny, R.

doi:10.1088/0029-5515/34/9/i06

Cited by 189 publications

(179 citation statements)

References 13 publications

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“…The PTRANSP code [5][6][7][8] is used to generate predictions of ITER plasmas for use as benchmarking cases. The cases are listed in Table I.…”

Section: Benchmark Casesmentioning

confidence: 99%

“…The PTRANSP code [5][6][7][8] is used to generate predictions for the plasma conditions. The predictions are integrated and self-consistent in that the heating, current-drive, and beam torques are calculated using predicted plasma profiles.…”

Section: Appendix 1 -Ptransp Predictions Of the Benchmark Casesmentioning

confidence: 99%

“…The impurity is assumed to be only C with density 2 % of n e . GLF23 is run in the "option 2" mode discussed in [8] with the toroidal rotation and flow-shearing rate profiles computed by GLF23. This results in predictions achieve moderately high central temperatures even with low pedestal temperatures.…”

Section: Appendix 1 -Ptransp Predictions Of the Benchmark Casesmentioning

confidence: 99%

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Benchmarking ICRF Full-wave Solvers for ITER

2011

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Benchmarking of full-wave solvers for ICRF simulations is performed using plasma profiles and equilibria obtained from integrated self-consistent modeling predictions of four ITER plasmas. One is for a high performance baseline (5.3 T, 15 MA) DT H-mode. The others are for half-field, half-current plasmas of interest for the pre-activation phase with bulk plasma ion species being either hydrogen or He 4 . The predicted profiles are used by six full-wave solver groups to simulate the ICRF electromagnetic fields and heating, and by three of these groups to simulate the current-drive.Approximate agreement is achieved for the predicted heating power for the DT and He 4 cases. Factor of two disagreements are found for the cases with second harmonic He 3 heating in bulk H cases. Approximate agreement is achieved simulating the ICRF current drive.

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“…The PTRANSP code [5][6][7][8] is used to generate predictions of ITER plasmas for use as benchmarking cases. The cases are listed in Table I.…”

Section: Benchmark Casesmentioning

confidence: 99%

Section: Appendix 1 -Ptransp Predictions Of the Benchmark Casesmentioning

confidence: 99%

Section: Appendix 1 -Ptransp Predictions Of the Benchmark Casesmentioning

confidence: 99%

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Benchmarking ICRF Full-wave Solvers for ITER

2011

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“…29 The second approach uses Monte Carlo modeling as implemented in the TRANSP code. 30 TRANSP follows 10 000 weighted beam particles and includes drift-orbit averaging, charge-exchange, reionization of halo neutrals, rotation and electric field effects, and spatial diffusion associated with neoclassical transport. The full fitted profiles ͑Fig.…”

Section: Theoretical Modelingmentioning

confidence: 99%

Accurate measurements of the pitch-angle scattering of beam ions

Heidbrink

2002

Physics of Plasmas

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The pitch-angle scattering rate of a dilute population of 75 keV deuterium ions is measured in a well-diagnosed, relatively quiet, magnetically-confined deuterium plasma. Neutral particle diagnostics detect the fast-ion density in velocity space following a short 10 ms pulse of injected beam ions. The data are compared to the classical theory of diffusion in velocity space caused by many, small-angle, Coulomb-scattering events. Within uncertainties of Շ15%, the data confirm the classical theory.

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“…The baseline discharge for this evaluation is an extensively studied 3 AT discharge ͑#99411͒ with anomalous fast-ion transport. The TRANSP code 4 can include an ad hoc diffusion coefficient in its calculation of the beam-ion profile; the sensitivity of the signals to variations in D B is a useful figure-of-merit. Uncertainties associated with dependencies on other plasma parameters imply that the resolution in D B is likely to exceed 0.5 m 2 /s for all three techniques ͑Table I͒.…”

Section: Introductionmentioning

confidence: 99%

Conceptual design of beam-ion profile diagnostics for the DIII-D tokamak

Heidbrink

Cross

Krasilnikov

2003

Review of Scientific Instruments

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Three diagnostic concepts that measure the radial profile of deuterium beam ions are assessed. One diagnostic exploits 3 MeV protons that are lost on their first orbit. Since beam-plasma reactions usually predominate in the discharges of interest, the beam-ion density profile can be inferred from the d-d fusion reaction profile. The relatively modest plasma current ͑ϳ1.6 MA͒ implies that a significant fraction of the charged d-d fusion reaction products are unconfined. The second diagnostic employs a neutron collimator. For this diagnostic, neutron scattering is a major concern. Both fusion product diagnostics are sensitive to uncertainties in the thermonuclear rate, so the anomalous beam-ion transport must exceed D B տ1.0 m 2 /s to be detectable. The third diagnostic employs an array of natural diamond detectors that is configured to measure the signal from beam ions that charge exchange with neutrals in a modulated heating beam. The sensitivity to uncertainties caused by pitch-angle scattering of the beam ions can be minimized by a prudent choice of detection angle. Because of attenuation of the escaping neutrals the effective resolution is D B ϳ0.5 m 2 /s.

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A standard DT supershot simulation

Cited by 189 publications

References 13 publications

Benchmarking ICRF Full-wave Solvers for ITER

Benchmarking ICRF Full-wave Solvers for ITER

Accurate measurements of the pitch-angle scattering of beam ions

Conceptual design of beam-ion profile diagnostics for the DIII-D tokamak

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