Development of ramp up design workflow on CFETR Integrated Design Platform

Liu, Li; Wang, Ming; Mao, Shaohua; Guo, Youming; Luo, Z.P.; Xiang, Jian; Liu, Xufeng; Zu, Chen; Chan, V. S.; Ye, Minyou

doi:10.1016/j.fusengdes.2017.04.005

Cited by 4 publications

(5 citation statements)

References 11 publications

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“…[17,18] This study designs and optimizes the magnetic diagnostics layout for the reconstruction of the equilibrium of the plasma according to the scientific objectives, engineering design parameters, and limitations of the CFETR. According to the CFETR discharge simulation, [19] the magnetic measurement data of the complete discharge was simulated by EFIT code, and the consistent plasma equilibrium was reconstructed accordingly, which verified the effectiveness of the magnetic diagnostics layout design. On this basis, the TSVD method is used to optimize the number and location of magnetic diag-nostics, and the redundancy reliability of the design is verified.…”

Section: Introductionmentioning

confidence: 76%

“…The Tokamak Simulation Code (TSC) can be used to simulate the time-dependent plasma performance in different phases of the discharge, including ramp-up, flat-top, and rampdown. [19,20] CFETR has a variety of discharge parameters with different power levels, and in this paper, the 200-MW operating scenario in Table 1 of Ref. [2] is selected, in a flat-top slice (t = 50 s, I p = 10 MA, β p = 0.081, and l i = 1.02) for validation.…”

Section: Optimizing the Number Of Magnetic Diagnostics Based On Tsvdmentioning

confidence: 99%

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Magnetic diagnostics layout design for CFETR plasma equilibrium reconstruction

Yu 于,

Huang 黄,

Luo 罗

et al. 2024

Chinese Phys. B

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Plasma equilibrium reconstruction provides essential information for tokamak operation and physical analysis. An extensive and reliable set of magnetic diagnostics is required to obtain accurate plasma equilibrium. This study designs and optimizes the magnetic diagnostics layout for the reconstruction of the equilibrium of the plasma according to the scientific objectives, engineering design parameters, and limitations of the Chinese Fusion Engineering Test Reactor (CFETR). Based on the CFETR discharge simulation, magnetic measurement data are employed to reconstruct consistent plasma equilibrium parameters, and magnetic diagnostics’ number and position are optimized by truncated Singular value decomposition, verifying the redundancy reliability of the magnetic diagnostics layout design. This provides a design solution for the layout of the magnetic diagnostics system required to control the plasma equilibrium of CFETR, and the developed design and optimization method can provide effective support to design magnetic diagnostics systems for future magnetic confinement fusion devices.

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Section: Introductionmentioning

confidence: 76%

Section: Optimizing the Number Of Magnetic Diagnostics Based On Tsvdmentioning

confidence: 99%

Magnetic diagnostics layout design for CFETR plasma equilibrium reconstruction

Yu 于,

Huang 黄,

Luo 罗

et al. 2024

Chinese Phys. B

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“…With experimental conditions (temperature, density, current and equilibrium information) provided from TSC, ONETWO [24] can call various code packages to compute the power deposition and current drive profiles of auxiliary heating and return them back to TSC. The converged results can be obtained by iteration with standardized data exchanges and iteration criterions in the scenario design workflow on the CFETR integrated design platform [12]. The NB source model is the Monte Carlo code NUBEAM [25].…”

Section: Computational Modelsmentioning

confidence: 99%

“…The CFETR geometry structures including coils and passive structures have been built as a digital tokamak in the TSC (as shown in figure 1). The corresponding 3D structures are shown in [12]. The constructed geometry structures are based on the CFETR conceptual design [1,28], which is available on CFETR Integrated design platform.…”

Section: Physic Models and Scenario Assumptionmentioning

confidence: 99%

“…Coupling the poloidal field systems controller and passive conductors, the free boundary equilibrium solver, auxiliary heating, current and temperature profile evolution dynamics is a very challenging task for both physics and engineering. The tool we use for time-dependent simulation is the tokamak simulation code (TSC) [10,11] coupled with some auxiliary heating subroutine packages, which is being applied as a workflow for scenario designs on the CFETR integrated design platform [12][13][14].…”

Section: Introductionmentioning

confidence: 99%

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The time-dependent simulation of CFETR baseline steady-state scenarios

et al. 2018

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One of the key issues to achieve the phase I mission of China fusion engineering test reactor (CFETR) is steady-state operation with a modest fusion power up to 200 MW. To study this feasibility, time-dependent modeling of CFETR baseline scenario is performed. The time-dependent scenario design examines actual discharge features, including auxiliary heating and current drive scheme, equilibrium, transport, PF coil systems and plasma control system during the plasma evolution. During plasma current ramp-up, 10 MW of EC or LH heating is used to effectively save volt–second consumption to a reasonable level within magnet coil capability and to reduce li for better plasma control. Three reference scenarios are designed to target full non-inductive operation with different external heating and current drive (H&CD), which are NB + EC, NB + LH, and LH + EC, respectively. Two scenarios with neutral beams reach the required fusion power of CFETR phase I target, while for LH + EC scenario the fusion power and confinement is somewhat lower. A reversed magnetic shear with is sustained with off-axis current drive and bootstrap current for all cases examined. Ideal MHD analysis shows that both large toroidal mode number n ballooning mode and low n kink mode are stable in the three reference cases independent of whether the current is totally relaxed or not. The L mode and H–L back transition ramp-down are designed to successfully reduce the plasma current to 2 MA and keep li below 2 with ramp-down rate of 80 kA s−1. The H–L back transition ramp-down yields improvements in the power transfer and coil current evolution as well as the li evolution. The heating and current drive characteristics of three auxiliary heating sources are indicated by scanning studies. A 2D scan of NB energy and tangency radius indicates the features of NB power deposition, current drive, torque and shine through issue. Both ramp-up and flattop are considered in the scanning of radio frequency parameters. For EC waves, the ramp-up phase constrains the parameter space more. The 2D scan of EC launch angle shows that EC waves launched above the midplane yield a better CD efficiency than using a midplane launcher. Specifically, 10 MW of EC waves launched from LFS above the midplane yield a maximum on axis driven current of about 0.55 MA, while waves launched from top yield a maximum near edge driven current of about 0.45 MA in the region of . Scanning of in LH spectrum shows that should be set around 1.7 to get enough penetration (inside ) for current drive and avoid strong accessibility problem. It is found that LH waves launched from HFS drives more current than that launched from LFS when is small. The maximum LH driven current reaches 1.1 MA with 10 MW of LH power launched from HFS.

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CFETR integration design platform: overview and recent progress

Mao

et al. 2019

Fusion Engineering and Design

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Development of ramp up design workflow on CFETR Integrated Design Platform

Cited by 4 publications

References 11 publications

Magnetic diagnostics layout design for CFETR plasma equilibrium reconstruction

Magnetic diagnostics layout design for CFETR plasma equilibrium reconstruction

The time-dependent simulation of CFETR baseline steady-state scenarios

CFETR integration design platform: overview and recent progress

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