2018
DOI: 10.1088/2058-6272/aac8d5
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Design of the poloidal field system for KTX

Abstract: The design of the poloidal field (PF) system includes the ohmic heating field system and the equilibrium (EQ) field system, and is the basis for the design of a magnetic confinement fusion device. A coupling between the poloidal and plasma currents, especially the eddy current in the stabilizing shell, yields design difficulties. The effects of the eddy current in the stabilizing shell on the poloidal magnetic field also cannot be ignored. A new PF system design is thus proposed. By using a low-μ material (μ=… Show more

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Cited by 4 publications
(3 citation statements)
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“…An optimization method for the breakdown based on the inverse reconstruction of magnetic fluxes has been investigated in the JT-60SA [21]. To achieve the optimal null field region, a specially designed poloidal field system was implemented for the KTX device [22]. Note that experimental examination of the null field region is necessary to study stray fields generated by external currents.…”
Section: Closed Boundary Analysismentioning
confidence: 99%
“…An optimization method for the breakdown based on the inverse reconstruction of magnetic fluxes has been investigated in the JT-60SA [21]. To achieve the optimal null field region, a specially designed poloidal field system was implemented for the KTX device [22]. Note that experimental examination of the null field region is necessary to study stray fields generated by external currents.…”
Section: Closed Boundary Analysismentioning
confidence: 99%
“…In contrast, the magnetic grating ruler can bear very high speeds and shocks without contact. The probe system is in the 'nearly zero' magnetic field region less than 20 Gauss in the middle plane, and the discharge magnetic field influence on the magnetic grating ruler can be ignored [29]. The output signals of the magnetic grating ruler are two quadrature TTL pulse time serials, which implement a minimum measurement resolution of 5 μm and determine the direction of movement.…”
Section: Control and Data Acquisition Systemsmentioning
confidence: 99%
“…Early reversed field pinches (RFPs) [10][11][12][13] have rarely equipped with reciprocating probe due to short discharge durations. However, a plasma profile diagnostic tool is urgently needed for Keda Torus eXperiment (KTX) [14][15][16][17][18][19][20][21][22][23][24][25][26][27][28][29] RFP. According to the experiences on tokamaks, a fast scanning probe system is designed to measure the plasma edge potential, density, and temperature profiles on the KTX RFP.…”
Section: Introductionmentioning
confidence: 99%