Minority Ion Research Articles

Neutral particle analysis of ICRF heated discharges on Alcator C-Mod

A neutral particle analyser (NPA) has been used to make measurements of the ion distribution in the Alcator C-Mod tokamak. We have used the analyser to measure the energy distribution of majority deuterons and minority hydrogen (up to 20 keV) at 0.4⩽r/a⩽0.6, during minority ion cyclotron range of frequencies (ICRF) heating. These energy spectra were also simulated by using the predicted minority ion distribution from a combined Fokker Planck ICRF code in a model for the neutral particle flux. The model predictions for neutral flux were found to be in qualitative agreement with the measured energy spectra. The energy spectra for two different ICRF antenna configurations were also measured and found to be very similar.

Mechanism of radial redistribution of energetic trapped ions due to m=2/n=1 kink instability in plasmas with an internal transport barrier in the Joint European Torus

Internal radial redistribution of MeV energy ion cyclotron resonance frequency driven hydrogen minority ions was inferred from neutral particle analyzer measurements during large amplitude magnetohydrodynamic activity in plasmas with an internal transport barrier in the Joint European Torus. A theory is developed for energetic ion redistribution during a m=2/n=1 kink mode instability. Plasma motion during the instability or during subsequent magnetic reconnection generates an electric field which can change the energy and radial position of the energetic ions. The magnitude of ion energy change depends on the value of the safety factor at the plasma core, q(0) from which the energetic ions are redistributed. A relation is found for the corresponding change in canonical momentum Pφ, which leads to radial displacement of the ions. The model yields distinctive new features of energetic ion redistribution such as more vertical particle displacement as q(0) increases from 1 to 2. Predicted characteristics of ion redistribution are compared with the measurements, and good correlation is found. Sometimes the energetic ions were further transported to the plasma edge due to interaction with a long-lived magnetic fluctuation (often in the form of a magnetic island) with chirping frequency in the laboratory frame which developed after the m=2/n=1 kink instability. Convection of resonant ions trapped in a radially moving phase-space island is modeled to understand the physics of such events.

Equilibrium and low-frequency stability of a uniform density, collisionless, spherical Vlasov system

Equilibrium and stability of a collisionless, spherical Vlasov system with uniform density are considered. Such an electron system is useful for the Periodically Oscillating Plasma Sphere (POPS) fusion system. In POPS the space charge of a uniform-density spherical electron cloud provides a harmonic well for an under-dense thermal ion population. Previous special solutions [D. C. Barnes, Phys. Plasmas 6, 4472 (1999)] are extended to arbitrary energy dependence. These equilibrium distribution functions and their first derivatives may be made nonsingular, in contrast to the previous solutions. Linear stability of general spherical equilibria is considered, and reduced to a one-dimensional calculation by the introduction of a spherical harmonic decomposition. All azimuthal mode numbers are degenerate. Using this formalism, the low-frequency stability of a collisionless, spherical Vlasov electron system coupled to a minority ion cloud is studied for the class of uniform-density electron equilibria found. In the low-frequency (adiabatic) limit, the general kinetic stability formalism can be integrated to find a closed form for the response of electron number density. The adiabatic response operator is shown to be self-adjoint. Computation of its eigenvalues proves the constant-density electrons/thermal ions system in POPS to be mostly stable to ion-electron electrostatic modes. Unstable modes are avoided unless central electrons have an extremely small energy spread. These results may also be useful for the consideration of gravitational and beam systems.

Predictive simulations of radio frequency heated plasmas of Tore Supra using the Multi-Mode model

Multichannel integrated predictive simulations using the Multi-Mode transport model are carried out for radio frequency heated Tore Supra tokamak discharges in which helium is the primary ion component. Lower hybrid heated discharges in which the total current is driven noninductively [X. Litaudon et al., Plasma Phys. Controlled Fusion 43, 677 (2001)] and a discharge with ion cyclotron radio frequency heating of the hydrogen minority ions [G. T. Hoang et al., Nucl. Fusion 38, 117 (1998)] are simulated. The simulations of these discharges represent the first test of the Multi-Mode model in helium plasmas with dominant electron heating. Also for the first time, the particle transport in Tore Supra discharges is computed and the density profiles are predicted self-consistently with other transport channels. It is found in these simulations that the anomalous transport driven by trapped electron mode turbulence is dominant compared to the transport driven by the ion temperature gradient turbulence. The feature of the Multi-Mode model to calculate the impurity transport self-consistently with other transport channels is used in this study to predict the influence of carbon impurity influx on the discharge evolution.

Neutron emission spectroscopy of radio frequency heated (D)T plasmas

The energy spectrum of the d+t→α+n neutron emission has been measured in experiments carried out at JET for plasmas of deuterium–tritium subjected to minority ion cyclotron resonance heating (ICRH) tuned to deuterium. The data obtained with the magnetic proton recoil spectrometer were of sufficient quality to distinguish up to three spectral components of neutron emission some of which were time resolved. A new analysis model was used to derive information on the underlying deuteron velocity distributions and their corresponding energy densities in the plasma. This experiment represents the first use of neutron emission spectroscopy for detailed diagnosis of the response of fusion plasmas to the applied ICRH power for different plasma conditions, including the time evolution over the heating pulse duration for individual discharges. In particular, ICRH effects on the plasma, together with the power absorption mechanisms, were studied as a function of the minority ion concentration in the range 9–20%.

On properties of compressional Alfvén eigenmode instability driven by superAlfvénic ions

Properties of the instability of compressional Alfvén eigenmodes (CAEs) in tokamak plasmas are studied in the cold plasma approximation with an emphasis on the instability driven by the energetic minority ion cyclotron resonance heating (ICRH) ions. The goal of the paper is to address a long standing problem of CAE half proton cyclotron harmonic excitation observed in pure deuterium plasma basing on new observations from Joint European Torus. As an example we apply earlier developed theory (Gorelenkov N.N. and Cheng C.Z. 1995 Nucl. Fusion 35 1743) to compare two cases: ion cyclotron emission (ICE) driven by charged fusion products and ICRH minority-driven ICE (MICE) (Cottrell G.A. 2000 Phys. Rev. Lett. 84 2397) recently observed on JET. Particularly in MICE spectrum, only instabilities with even harmonics of deuterium cyclotron frequency at the low-field-side plasma edge were reported. Odd deuterium-cyclotron frequency harmonics of ICE spectrum with frequencies between the integer cyclotron harmonics of protons can be driven only via the Doppler shifted cyclotron wave–particle resonance of CAEs with fusion products, but are shown to be damped due to the electron Landau damping in experiments on MICE. Excitation of odd harmonics of MICE with high-field-side heating is predicted. Dependence of the MICE instability on the electron temperature is studied and is shown to be strong. Low electron β is required to excite odd harmonics of MICE.

Modelling of Alfvén waves in JET plasmas withthe CASTOR-K code*

A hybrid magnetohydrodynamic (MHD)-gyro-kinetic model CASTOR-K developed for the study of Alfvén eigenmode (AE) stability in the presence of energetic ions has been applied to the interpretation of recent measurements of Alfvén waves in JET. These include the detailed AE damping measurements performed using the AE antenna excitation system and also the observations of Alfvén cascades in strongly reversed shear scenarios at JET. The mode conversion between the AEs and kinetic Alfvén waves and the relation to the Alfvén continuum is studied and the calculated damping is compared with the experimental data. The contribution of ion cyclotron resonant heating driven minority ions to the growth rate of the novel-type mode localized around the point of zero magnetic shear is calculated. This mode is shown to be clearly linked to the ideal MHD `Alfvén continuum', computed with the CSCAS code and consistent with the observation of a quasi-periodic pattern of upward frequency sweeping Alfvén cascades in JET.

Study of acceleration and confinement of high-energy protons during ICRF and NBI heating in LHD using a natural diamond detector

Energetic tail formation by ion-cyclotron-range-of-frequencies (ICRF) heating was studied in the large helical device (LHD), by measuring high-energy charge-exchange atom spectra with a specially developed natural diamond detector, which views the LHD plasma perpendicularly. Comparison of measured effective perpendicular temperature of ICRF-driven H+ minority ions with the classical Stix model indicates that perpendicular ions with energy at least up to 150 keV are well confined in the centre region of the LHD. However, deviation from the classical prediction was observed for high-energy perpendicular protons in the outer region of the plasma, indicating ripple-induced transport and charge-exchange losses. With perpendicular fast atom spectrum and flux measurements, small yet notable differences were detected co-injected and counter-injected ICRF-driven beam ion confinement during combined neutral beam injection (NBI) and ICRF heating. These results can be explained by the differences in the orbit topology and ICRF-induced drift.

Double transport barrier experiments on Alcator C-Mod

Double transport barrier modes (simultaneous core and edge transport barrier) have been observed with off-axis ion cyclotron range of frequencies (ICRF) heating in the Alcator C-Mod tokamak [I. H. Hutchinson et al., Phys. Plasmas 1, 1511 (1994)]. An internal transport barrier (ITB) is routinely produced in enhanced DαH-mode (EDA) discharges where the minority ion cyclotron resonance layer is at r/a∼|0.5| during the current flat top phase of the discharge. The density profile becomes peaked without the presence of a particle source in the plasma core and continues to peak until the increased core impurity radiation arrests the improved energy confinement, ultimately leading to a barrier collapse. With the addition of moderate (0.6 MW) central ICRF heating, the double barrier mode was maintained for as long as the ICRF power was applied. Modeling shows that the internal thermal barrier was maintained throughout the discharge. The presence of sawteeth throughout most of the ITB discharge allows sawtooth-induced heat pulse analysis to be performed. This analysis indicates that there is an abrupt radial discontinuity in the heat pulse time to peak profile when an ITB is present. Furthermore, this discontinuity appears to move into the core plasma from the edge region in about 0.2 s, several confinement times. The deduced thermal diffusivity, χhp, indicates that a barrier exists in the electron thermal transport, the barrier is limited to a narrow radial region, and the transport is unaffected outside this narrow radial extent.

Advances in full-wave modeling of radio frequency heated, multidimensional plasmas

Previous full-wave models for rf heating in multidimensional plasmas have relied on either cold-plasma or finite Larmor radius approximations. These models assume that the perpendicular wavelength of the rf field is much larger than the ion Larmor radius, and they are therefore limited to relatively long wavelengths and low cyclotron harmonics. Recently, alternate full-wave models have been developed that eliminate these restrictions. These “all orders spectral algorithms” take advantage of new computational techniques for massively parallel computers to solve the integral form of the wave equation in multiple dimensions without any restriction on wavelength relative to orbit size, and with no limit on the number of cyclotron harmonics retained. These new models give high-resolution, two-dimensional solutions for mode conversion and high harmonic fast wave heating in tokamak geometry. In addition, they have been extended to give fully three-dimensional solutions of the integral wave equation for minority ion cyclotron heating in stellarator geometry. By combining multiple periodic solutions for individual helical field periods, it is possible to obtain complete wave solutions valid over the entire volume of the stellarator for arbitrary antenna geometry.

Radio-frequency-driven radial current and plasma rotation in a tokamak

Plasma rotational shear is potentially important for controlling the formation and positioning of internal transport barriers that could stabilize tokamak microturbulence and improve plasma confinement. A new physical mechanism capable of inducing plasma rotation and rotational shear via the ion cyclotron resonance frequency (ICRF) heating of minority ion species in a tokamak has been proposed [Perkins, White, Bonoli, and Chan, Phys. Plasmas 8, 2181 (2001)]. The present work evaluates the validity of this mechanism under the realistic condition when fast ions are continuously heated and slowed down in a driven system. Ion dynamics are calculated with a Monte Carlo code in which wave-induced diffusion in velocity space is accounted for by a quasilinear operator. The code follows the drift trajectories of test particles in a tokamak geometry under the influence of given rf fields and collisions with the background plasma. When the heating geometry is such that no net toroidal wave momentum is injected, the rotational characteristics described in Perkins et al. are reproduced. A physical picture emerges which ascribes the directionality of the rotation as a consequence of finite drift orbit width. The stochastic nature of the wave-induced diffusion can result in a net toroidal torque on the bulk plasma. A number of predicted features can be experimentally tested as a validation of finite orbit drift physics and radio-frequency-induced orbit diffusion.

First observation of pT fusion in JET tritium plasmas with ICRF heating of protons

High power ICRF heating of a hydrogen minority ion species in JET tritium plasmas has generated a total neutron rate that is about 40% larger than the 14 MeV neutron rate originating from fusion reactions between bulk tritium ions and deuterium minority ions. The T(p,n)3He fusion reaction, caused by ICRF accelerated protons, is identified as a source for producing the excess neutron emission. This reaction is endothermic and has a proton energy threshold of about 1 MeV and a peak cross-section at about 3.0 MeV. The presence of protons with such high energies is detected in gamma ray and high energy neutral particle analyser measurements and is also confirmed by ICRF modelling with the PION code. The fast proton energy content and the pT fusion reactivity as simulated by the PION code are compared with the experimental measurements when classical slowing down and confinement of ICRF accelerated protons are assumed in the simulations.

Ion and electron heating in ICRF heatingexperiments on LHD

The ICRF heating experiments conducted in 1999 in the third experimental campaign on LHD are reported, with an emphasis on the optimization of the heating regime. Specifically, an exhaustive study of seven different heating regimes was carried out by changing the radiofrequency relative to the magnetic field intensity, and the dependence of the heating efficiency on H minority concentration was investigated. It was found in the experiment that both ion and electron heating are attainable with the same experimental set-up by properly choosing the frequency relative to the magnetic field intensity. In the cases of both electronheating and ion heating, the power absorption efficiency depends on the minority ion concentration. An optimum minority concentration exists in the ion heating case while, in the electron heating case, the efficiency increases with concentration monotonically. A simple model calculation is introduced to provide a heuristic understanding of these experimental results. Among the heating regimes examined in this experiment, one of the ion heating regimes was finally chosen as the optimized heating regime and various high performance discharges were realized with it.

On the role of ion heating in ICRF heated discharges in Tore Supra

The effect of bulk ion heating in Tore Supra has been investigated by studying discharges with varying concentrations of minority ions during ICRF hydrogen minority heating in deuterium/4He plasmas. As expected, the level of bulk ion heating is found to increase with the minority concentration. Higher levels of ion heating are shown to be accompanied by two significant effects: an improved energy confinement and a strong influence on the plasma rotation.

Chaotic regime of Alfvén Eigenmode wave-particle interaction.

The chaotic regime in Alfvén eigenmode wave-particle interaction is identified for the first time in the tokamak plasma of the Joint European Torus. The Alfvén modes are driven by energetic hydrogen minority ions produced by ion cyclotron resonance heating. The experimental signatures of the chaotic regime include spectral broadening, phase flips, and nonperiodic amplitude variations. These phenomena are found to be consistent with a general nonlinear theory of kinetic instabilities near stability threshold developed by Berk, Breizman, and Pekker.

Poloidal field effects on fundamental minority ion cyclotron resonance heating in a tokamak plasma

Minority ion fundamental cyclotron resonance is studied in a large tokamak in which the geometrical optics approximation applies off resonance and the minority average speed is less than the wave phase speeds. Poloidal equilibrium magnetic field effects are included, which lead to nontrivially nonlocal integrodifferential equations for the wave fields. Exact reciprocity relation is given as well as explicit analytic solutions for the transmission coefficients for both the high and low field side incidences. Numerical solutions are needed only for the high field side incident reflection coefficient. Numerical schemes are described and numerical results are presented together with a reliable error bound. Typically, energy absorption increases with poloidal field. The energy absorption increases with minority density at low values of minority density. However, it decreases at high minority density. Poloidal field effects weaken the dependence of energy absorption on the toroidal wave number.

Fast ion density measurements using high energy neutral particleanalysis in JET

In the JET tokamak the perpendicular velocity distribution function ofICRF heated ions is inferred in the energy range 0.3 ⩽ E (MeV) ⩽ 1.5 from neutral particle analysermeasurements of the emitted high energy atomic flux. The measurements areintegrated along a vertical line of sight through the plasmacentre, with a finite viewing solid angle. A method is presented todeduce the ICRF heated minority ion density in the plasma centretaking into full consideration the geometry of the measurements. Theresults are verified against independent measurements of fast iondensity and perpendicular energy content, and quantitativeagreement is obtained. These results further validate the model of impurity inducedneutralization, which was developed to interpret the high energyatomic flux measurements in JET. They give access to fundamentalproperties of the ICRF heated ion distribution function, and provideimproved tools for understanding the behaviour of fast ion populationsin forthcoming fusion plasma experiments.

Investigation of fast particle driven modes on Alcator C-Mod

High-frequency coherent magnetic fluctuations have been observed with hydrogen minority ion cyclotron resonant frequency (ICRF) heating in Alcator C-Mod in low- or reversed-shear current rise conditions. The mode frequencies (150-450 kHz) are in the range expected for toroidal Alfvén eigenmodes (TAEs) with central q values greater than unity. These modes have low n3 and appear to rotate in the ion diamagnetic drift direction. Under these relatively low-density current rise conditions with low or reversed magnetic shear, TAEs can be destabilized by a predicted fast hydrogen ion tail of just over 100 keV. Calculations with the CASTOR code indicate that a broad eigenmode can exist with a calculated frequency at the measured mode frequency, which falls in a clear TAE gap across the profile. The frequency of the current rise modes can increase or decrease rapidly from 150 to 400 kHz in less than 15 ms, which cannot be explained by linear theory. In some cases, only a single mode is excited with a linearly increasing frequency, in contrast to the multiple modes with decreasing frequency usually observed on other devices.

The first ICRF heating experiment in the large helical device

The first experiment of the ion cyclotron range of frequencies (ICRF) heating in the Large Helical Device (LHD) was carried out at the end of 1998. The LHD is a large superconducting heliotron device and its first plasma was produced in March 1998. During the ICRF heating experiment, a maximum 300 kW/0.2 s of ICRF power was injected into the LHD plasma by using a pair of loop antennae. This paper reports on the installation of the loop antennae, the results of antenna coupling and the first heating experiments. The antennae are designed to operate in the steady state and to change their distance from the plasma by 0-15 cm. In the experiment, the antenna resistance coupled with the plasma was measured by changing the distance between the last closed flux surface and the launcher front from 9 cm to 5 cm. The resistance was almost doubled by decreasing the distance. The target plasma was produced by the second harmonic electron cyclotron heating (ECH) of 84 GHz gyrotrons at a magnetic field of 1.5 T and a low plasma electron density of less than 1 × 1019 m-3. Therefore, the low coupling resistance limited the maximum injected power to less than 300 kW. The heating efficiency and heating species were varied by the minority ion gas-puffing rate. The heating characteristics were compared with a one-dimensional full-wave analysis code, and the experimental results were consistent with wave damping analysis. For the optimum condition of the minority hydrogen gas-puff ratio, the plasma internal energy increased from 13 kJ to 26 kJ by almost the same power as the ECH power.

Sawtooth evolution during JET ion-cyclotron-resonance-heated pulses

The recent Joint European Torus deuterium-tritium campaign has yielded ion-cyclotron-resonance-heated (ICRH) pulses during which both the sawtooth characteristics and the ICRH minority ion population both evolve substantially. At multiple times during each pulse, the evolution of the kinetic-fluid MHD energy is calculated from measurement of the energetic ions and compared with the evolving sawtooth duration. There is strong correlation between sawtooth duration and minority ion stabilization of the ideal internal kink.