Chapter 2: Magnetic Diagnostics

Strait, E. J.; Fredrickson, E. D.; Moret, J.-M.; Takechi, M.

doi:10.13182/fst08-a1674

Cited by 88 publications

(43 citation statements)

References 153 publications

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“…Therefore a reference signal equal to the vacuum toroidal magnetic flux is usually subtracted from it, giving a net toroidal flux equal to the diamagnetic flux D ∆Φ produced by the circular plasma. Relation between the diamagnetic flux and the poloidal beta derived from simplified equilibrium relation [3,6] …”

Section: Measurements Of Eight Of the Plasmamentioning

confidence: 99%

“…Also measurement of plasma energy with diamagnetic loop and measurement of plasma density with Langmuir probe gives a value of plasma temperature. Energy confinement time, plasma resistance, and also the plasma pressure are also can be determined from diamagnetic loop [1][2][3][4][5][6][7][8]. In this paper we presented experimental magnetic diagnostic methods on IR-T1, which it is a small, low beta and large aspect ratio tokamak with a circular cross section (see Table 1).…”

Section: Introductionmentioning

confidence: 99%

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Simultaneous Simple Measurements of Tokamak Plasma Parameters Especially Based on Plasma Diamagnetic Effect

Elahi¹,

Ghoranneviss²

2012

JNPP

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Determinations of poloidal beta, internal inductance, plasma energy, plasma pressure, plasma temperature, plasma resistance, plasma effective atomic number, and plasma energy confinement time are essential for tokamak plasma experiments. In this paper an experimental methods especially based on diamagnetic loop (toroidal flux loop) for measurements of these parameters are presented. For this purposes a diamagnetic loop with its compensation coil and also an array of magnetic probes designed, constructed, and installed on outer surface of the IR-T1 tokamak. Also in this work we obtained the Shafranov parameter, plasma current, plasma voltage, and the plasma density from the magnetic probe, Rogowski coil, poloidal flux loop, and the Langmuir probe measurements, respectively.

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Section: Measurements Of Eight Of the Plasmamentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Simultaneous Simple Measurements of Tokamak Plasma Parameters Especially Based on Plasma Diamagnetic Effect

Elahi¹,

Ghoranneviss²

2012

JNPP

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“…Fro m this measurement, the total d iamagnetic energy content and the confinement time of the plasma can be obtained as well as the poloidal beta. On the other hand, the magnetic fields distribution outside the plasma and then the Shafranov shift depend on the combination of l is determined by the radial distribution of toroidal current profile of the plasma [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15]. In this paper we present two magnetic techniques based on the diamagnetic loop and magnetic probe for determination of the poloidal Beta and poloidal magnetic field, and moreover an appro ximated method for determination of the plasma internal inductance, and therefore the Shafranov parameter and Shafranov shift in IR-T1 To kamak, wh ich it is a small, low p β and large aspect ratio tokamak with a circular cross section (see Table 1).…”

Section: Introductionmentioning

confidence: 99%

Dependence of Tokamak Plasma Position to its Internal Inductance

Elahi¹,

Ghoranneviss²

2012

JNPP

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In this contribution we will p resented comparison of two techniques in order to investigate of the effects of internal inductance on tokamak p lasma position, based on a toroidal flu x loop (diamagnetic loop) and magnetic probes measurements. For this purpose, a diamagnetic loop with its co mpensation coil, and also array of magnetic probes were designed, constructed, and installed on outer surface of the IR-T1 tokamak chamber, and then the poloidal beta and poloidal and radial magnetic fields obtained. Moreover a few appro ximate values of the internal inductance for different possible profiles of the p lasma current density are also calculated. Then, the Shafranov parameter and also the Shafranov shift were determined. Experimental results compared. Co mparison of results on IR-T1, show that (1) by increasing the internal inductance from one, plas ma colu mn shifted inward, and also (2) IR-T1 p lasma current density profile relate to the power of 3 ≈ υ approximately.

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“…A wealth of literature exists describing HF magnetic diagnostic systems in existing fusion experiments, and the desirable requirements for the measurement of HF instabilities in present and future burning-plasma devices [2]. Summarizing from the available documentation, the target design parameters (effective area, electrical properties) for HF magnetic sensors in ITER should be such that this diagnostic system will be able to provide measurements of MHD instabilities in the frequency range between 10 kHz and up to ∼500 kHz (but not necessarily above 1 MHz), with magnitude as low as practically possible, in the range |ıB MEAS /B POL | ∼ 10 −6 or lower.…”

Section: Introductionmentioning

confidence: 99%

Assessment of the ITER high-frequency magnetic diagnostic set

Testa

Carfantan

Toussaint

et al. 2011

Fusion Engineering and Design

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a b s t r a c tThe ITER high-frequency (HF) magnetic diagnostic system has to provide essential measurements of MHD instabilities with |ıB MEAS /B POL | ∼ 10 −4 (∼1 G) for frequencies up to 2 MHz to resolve toroidal mode numbers (n) in the range |n| = 10 to |n| = 50. A review of the measurement requirements for HF MHD instabilities in ITER was initiated during the TW4 work-program and led to significant interest for physics and real-time control issues in measuring modes with |ıB MEAS | as low as ∼10 −3 G at the position of the sensors, with |n| ≤ 30 and poloidal mode numbers |m| ∼ 2|n| up to |n| ∼ 15, for a frequency range extending up to ∼500 kHz. We have examined the ability of the current ITER design for the individual sensors and the diagnostic system as a whole to meet these needs, and have explored what adjustments to the design (of the individual sensors and/or of the system as a whole) or to the requirements would be needed to meet them when considering different hypothesis for the financial costs and risk management over the ITER life-time. First, we find that the proposed diagnostic layout, with 168 sensors in total, does not meet the more stringent measurement requirements and risk management criteria: these can only be met by a revision of the design requiring 350-500 sensors, depending on different costing and risk management options. Second, we find that the current design for the ITER HF Mirnov-type pick-up coil could be usefully revised.

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Chapter 2: Magnetic Diagnostics

Cited by 88 publications

References 153 publications

Simultaneous Simple Measurements of Tokamak Plasma Parameters Especially Based on Plasma Diamagnetic Effect

Simultaneous Simple Measurements of Tokamak Plasma Parameters Especially Based on Plasma Diamagnetic Effect

Dependence of Tokamak Plasma Position to its Internal Inductance

Assessment of the ITER high-frequency magnetic diagnostic set

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