Case | R0 (m) | a (m) | B0 (T) | T⊥ (keV) | κn | κT |
CBC | 1.67 | 0.6 | 1.9 | 1.97 | 2.23 | 6.96 |
ITER | 6.2 | 2.0 | 5.3 | 10.0 | 3.0 | 6.0 |
CFETR | 5.7 | 1.6 | 5.0 | 12.5 | 3.93 | 8.91 |
Citation: | Debing ZHANG, Limin YU, Erbing XUE, Xianmei ZHANG, Haijun REN. Anomalous transport driven by ion temperature gradient instability in an anisotropic deuterium-tritium plasma[J]. Plasma Science and Technology, 2022, 24(2): 025104. DOI: 10.1088/2058-6272/ac42bc |
In this work, the anomalous transport driven by the ion temperature gradient instability is investigated in an anisotropic deuterium-tritium (D-T) plasma. The anisotropic factor α, defined as the ratio of perpendicular temperature to parallel temperature, is introduced to describe the temperature anisotropy in the equilibrium distribution function. The linear dispersion relation in local kinetic limit is derived, and then numerically evaluated to study the dependence of mode frequency on the anisotropic factor α of D and the fraction of T particle εT by choosing three sets of typical parameters, denoted as the cyclone base case, ITER and CFETR cases. Based on the linear results, the mixing length model approximation is adopted to analyze the quasi-linear particle and energy fluxes for D and T. It is found that choosing small α and large εT is beneficial for the confinement of particle and energy for D and T. This work may be helpful for the estimation of turbulent transport level in the ITER and CFETR devices.
The confinement of particle and energy is a key issue in tokamaks. Since the experimental observation of the anomalous ion thermal transport in DIII-D tokamak [1], the research for the heat transport has been developed prosperously. The ion temperature gradient (ITG) instability is considered to play an important role in the anomalies in ion thermal transport [2, 3].
The fusion temperature can be reached through the intense auxiliary heating, such as the neutral beam injection (NBI) heating, ion cyclotron resonance heating (ICRH) as well as electron cyclotron resonance heating. These heating regimes have been widely used in the existent tokamaks such as EAST, JET, DIII-D, and will be adopted in the fusion tokamaks such as ITER and CFETR for the realization of deuterium-tritium (D-T) discharge. Nevertheless, the auxiliary heating regimes could produce strong plasma anisotropy. Generally, tangentially injected NBI drives the anisotropy with T‖ > T⊥,and the ICRH typically generates perpendicularly dominant anisotropy with T⊥ > T‖,where T‖ and T⊥ are the parallel and perpendicular temperatures with respect to the magnetic field. Anisotropic plasma has been experimentally observed. For instance, studies in MAST suggest that the ratio T⊥ /T‖ = 1.7 is achieved [4]. In EAST, the degree of the parallel-dominated anisotropy T‖ /T⊥ = 1.8 is reached at low electron density with low hybrid wave heating [5].
Influences of the temperature anisotropy on plasma behaviours have been widely researched. The temperature anisotropy plays important roles in the ITG instability [6], the resistive wall mode [7], the low-frequency electromagnetic wave [8], the geodesic acoustic mode [9–11], the zonal flows [12, 13] and so on. In detail, in [6], it is demonstrated that instability of ITG mode is reduced by an ion temperature anisotropy of higher perpendicular temperature or high enough parallel temperature. In [13], it is found that the residual zonal flow driven by the ITG instability shows a strong dependence on the temperature ratio
In this work, we focus on the ITG instability in a temperature anisotropic D-T plasma. The linear dispersion relation is theoretically derived and numerically solved to analyze the effects of temperature anisotropy on the linear behaviour of ITG instability; based on the linear results, the mixing length model approximation is adopted to analyze the anomalous particle and energy transport. The remaining part of this paper is organized as follows. In section 2, dispersion relation of the ITG instability in an anisotropic D-T plasma is derived; in section 3, the linear frequency of ITG instability is numerically evaluated; in section 4, by adopting the mixing length model approximation, the particle flux and energy flux driven by the ITG instability are analyzed; section 5 is the conclusion and discussion.
In this section, we derive the dispersion relation in an anisotropic D-T plasma. We consider the case with the electrostatic fluctuation δϕ(r, t), where r denotes the particle position. We introduce the Fourier transformation for the perturbed quantities
(1) |
where k is the wave vector and ω = ωr + iγ is the frequency with ωr and γ the real and imaginary part, respectively. The dispersion relation for ITG instability expressed in the Fourier representation is given by the quasi-neutrality condition
(2) |
Here, j denotes the ion species, which is adopted as D and T in this work. e is the elementary charge, Zj is the charge number of j-species.
Generally, for a ITG-dominated regime, the electron perturbed density is expressed with the adiabatic approximation, namely, with ne0 and Te the electron equilibrium density and temperature, respectively. The ion perturbed density is calculated as with \int \mathrm{d}^3 v the velocity space integration and the perturbed distribution function. In the following part, the calculations for the perturbed density of D and T are treated equally, and the label 'j' is omitted for simplicity when no ambiguity is introduced.
By neglecting the parallel effects, the perturbed distribution function is yielded from the gyrokinetic (GK) equations [16, 17]
\begin{aligned} \left\langle f_k\right\rangle= & e \phi_{\boldsymbol{k}}\left(1-J_0^2\right)\left(\partial_E F_0+\frac{1}{B} \partial_\mu F_0\right) \\ & +e \phi_{\boldsymbol{k}} J_0^2\left(\frac{-\omega_{\mathrm{d}} \partial_E F_0+\frac{1}{Z e B} \boldsymbol{b} \times \boldsymbol{k} \cdot \nabla F_0}{\omega-\omega_{\mathrm{d}}}\right). \end{aligned} | (3) |
Here, \langle A\rangle \equiv \frac{1}{2 \pi} \int_0^{2 \pi} \mathrm{d} \xi A denotes the gyro-average. F0 = F0(r, μ, E) is the equilibrium distribution function with r the radial coordinate, μ the magnetic moment and E the energy variable. B and b denote the amplitude and the direction of the background magnetic field. denotes the magnetic drift frequency, where kθ is the poloidal wavenumber, R is the major radius, θ is the poloidal angle, is the magnetic shear, T⊥ is the perpendicular temperature, and are the parallel and perpendicular velocities normalized by vt, ⊥,respectively, where with m the ion mass. is the 0th-order Bessel function, λs = kθρs, ρs = cs/Ω with the acoustic speed and Ω = ZeB/m the gyro-frequency. Note that in equation (3), the first term denotes the polarization part, the second term denotes the gyrocenter part. In appendix, we give a brief derivation of equation (3) based on the traditional GK theory [18] for the readers who are interested in.
Here, we make some remarks on equation (3). Generally, the trapped ion contribution is important when the frequency of perturbation is close to the ion bounce frequency. Note that the driving force for local ITG instability is due to the diamagnetic drift combined with temperature gradient, the trapped ion contribution can be neglected for simplicity. Besides, only the ion resonance due to the diamagnetic drift is kept and the parallel effect is neglected; the approximation about neglecting the parallel effect is justified when the mode is localized in the outer midplane [19]; correspondingly, we replace the local value of ωd with the value of θ = 0 in the following part.
To proceed, following the general introduction of anisotropy, we set the equilibrium distribution for each ion species as a bi-Maxwellian form [6, 8, 9, 13]
(4) |
where n0 is the equilibrium density. The analyses of the magnetic equilibrium in [9, 20] show that T‖ = T‖(ψ ), T⊥ = BT‖(ψ )/(B - C0(ψ )) with ψ(r) the magnetic surface variable, C0(ψ ) is any function with respect to ψ ; the forms of T‖ and T⊥ lead to ∂θF0 = 0. Besides, the total plasma current is found to be I=I_0(\psi)+\mathcal{O}[(\alpha-1) \beta], where α = T⊥ /T‖ is introduced to represent the temperature anisotropy, β is the ratio of plasma pressure to the magnetic pressure, I0(ψ ) is the total plasma current in an isotropic plasma. In a low-β plasma, the corrections to the magnetic field are very small and invariably ignored [9, 20]. So the magnetic equilibrium is considered as unaffected by the anisotropy in this work.
After calculating the necessary deviations of F0 and substituting them into equation (3), we obtain
\left\langle f_k\right\rangle=-\frac{e \phi_k}{T_{\perp}} F_0\left[\left(1-J_0^2\right)+J_0^2 \frac{-h_\nu R \mathcal{X}^\nu}{\hat{\omega}-\left(2 \hat{v}_{\|}^2+\hat{v}_{\perp}^2\right)}\right]. | (5) |
Here,
\mathcal{X}^1=-\partial_r \ln n_0, | (6a) |
\mathcal{X}^2=-\partial_r \ln T_{\perp}, | (6b) |
\mathcal{X}^3=-\partial_r \ln T_{\|}, | (6c) |
\mathcal{X}^4=-\partial_r \ln B, | (6d) |
\mathcal{X}^5=-\nabla r \cdot \kappa, | (6e) |
and a set of weighting functions
(7a) |
(7b) |
(7c) |
(7d) |
(7e) |
Here, κ is the magnetic curvature. In the large-aspect-ratio approximation, \mathcal{X}^4=\mathcal{X}^5=1 / R. Note that \mathcal{X}^4 h_4 originates from the temperature anisotropy, that is, when α = 1, this term vanishes; \mathcal{X}^5 h_5 comes from the diamagnetic drift term.
Next, we calculate the velocity integral of \left\langle f_k\right\rangle to obtain the perturbed density. Before the detailed calculation, we introduce the velocity transformation \left(\hat{v}_{\|}, \hat{v}_{\perp}\right) \rightarrow\left(\hat{v}_{\|}, \mathcal{E}\right) with \mathcal{E}=\hat{v}_{\|}^2+\hat{v}_{\perp}^2 / 2 to rigorously treat the magnetic drift [22], then \int \mathrm{d}^3 \boldsymbol{v}=2 \pi \int_0^{\infty} \mathrm{d} \mathcal{E} \int_{-\sqrt{\mathcal{E}}}^{\sqrt{\mathcal{E}}} \mathrm{d} \hat{v}_{\|}. After some straightforward calculation, the perturbed density can be formally written as
(8) |
Here, Γ0 = I0(b)e-b with I0 the modified 0th-order Bessel function of the first kind, . , and , where κn = R/Ln with , with and with . K_0=\int_0^{\infty} \mathrm{d} \mathcal{E} \frac{V_0}{2 \mathcal{E}-\hat{\omega}}, K_1=\int_0^{\infty} \mathrm{d} \mathcal{E} \frac{\mathcal{E} v_0}{2 \mathcal{E}-\hat{\omega}} and K_2=\int_0^{\infty} \mathrm{d} \mathcal{E} \frac{V_2}{2 \mathcal{E}-\hat{\omega}}, which represent the \mathcal{E}-integral in the velocity integral;
V_{2 n}(\mathcal{E})=\frac{4 \sqrt{\alpha}}{\sqrt{\pi}} \mathrm{e}^{-2 \mathcal{E}} \int_0^{\sqrt{\mathcal{E}}} \mathrm{d} \hat{v}_{\|} J_0^2 \mathrm{e}^{(2-\alpha)} \hat{v}_{\|}^2 \hat{v}_{\|}^{2 n}, |
which represents the
Note that in equation (8), the factor
(9) |
Here, we recover the label 'j' to emphasize the role of D and T in the dispersion relation. τj = T⊥,j/Te. εT = nT0/ne0 denotes the fraction of T, from which the fraction of D is calculated as εD = (1 - ZTεT)/ZD. By setting εT = 0 and αD = 1, equation (9) reduces to the well-known form with local kinetic limit [19, 23].
In this section, equation (9) is numerically evaluated to study the effects of the temperature anisotropy and the fraction of T on the linear frequency. For simplicity, only the temperature anisotropy for D is considered, that is, we set αT = 1; correspondingly, we denote αD as α for short in the following. Since the temperature anisotropy observed in the experiments can reach T⊥ /T‖ = 1.7 [4] and T‖ /T⊥ = 1.8 [5], we vary α from 1/2 to 2 in the following calculation; we mention that the perpendicular temperature is fixed, variation of α means variation of the parallel temperature T‖ . Besides, we set the perpendicular temperature of D to be the same as that of T, namely, T⊥,D = T⊥,T; the ITG anisotropy is neglected for simplicity. κT, D = κT, T and κn, D = κn, T are assumed. τD = τT = 1. We consider three typical cases: one is the cyclone base case (CBC) [24], which is widely-used in the GK simulation; the other two are the ITER standard scenario [25] and the CFETR steady-state scenario [26], for the purpose to investigate the ITG instability in the future fusion devices. The key parameters used in the three cases are shown in table 1; in each case, the ITG instability dominates [24–26].
Case | R0 (m) | a (m) | B0 (T) | T⊥ (keV) | κn | κT |
CBC | 1.67 | 0.6 | 1.9 | 1.97 | 2.23 | 6.96 |
ITER | 6.2 | 2.0 | 5.3 | 10.0 | 3.0 | 6.0 |
CFETR | 5.7 | 1.6 | 5.0 | 12.5 | 3.93 | 8.91 |
Equation (9) is solved as follows: for given (α, εT, kθρs, D), we scan
When α = 1/2, for a fixed kθρs, D, the real frequency decreases while the growth rate increases as εT increases; on the contrary, the real frequency increases while the growth rate decreases as εT increases when α = 2. In small kθρs, D region, dependence of the growth rate on εT is more obvious when α = 1/2 than those when α = 1 and 2. It is also indicated that the ITG instability is destabilized (stabilized) when α = 1/2 (α = 2) by increasing εT.
Figure 2 shows the real frequency and growth rate versus kθρs, D in the CBC case with three different T fractions εT = 0.0, 0.1 and 0.5, respectively; the temperature anisotropic factor α is varied from 1/2 to 2. It is shown that, tendencies of the dependence of real frequency on α at different εT are similar, that is, the real frequency decreases as α increases; the decrement is obvious in large kθρs, D and/or small εT region. Tendency of the dependence of growth rate on α is opposite to that of the real frequency. In detail, for a fixed εT, the growth rate increases as α increases, especially in large kθρs, D and/or small εT region. It is interesting to find that, in the region of α < 1, dependence of the growth rate on α is more significant compared to that in the region of α > 1. We take εT = 0.5 and kθρs, D = 0.4 as an example. When α increases from 1/2 to 1, the growth rate increases from about 0.38 to about 0.48, the increment is about 30%; when α increases from 1 to 2, the growth rate increases from about 0.48 to about 0.52, the increment is about 8%. It is indicated that the ITG instability may be significantly stabilized by controlling α < 1.
Besides, it is seen that as εT increases, the real frequency and growth rate with α ≠ 1 are close to those with α = 1. In another word, effect of the temperature anisotropy of D on the frequency becomes weaker with higher εT. Note that this result relates to the assumption that the temperature anisotropy is only from D; as εT increases, the fraction of D decreases, as a result, effect of the temperature anisotropy becomes weak.
Here, we give a phenomenological explanation about the dependence of linear frequency on α and εT shown in figures 1 and 2 from the point of diamagnetic drift resonance. kθρs, D is fixed in the analysis. The diamagnetic drift resonance occurs when
In figure 3, the real frequency and growth rate versus kθρs, D in the CBC, ITER and CFETR cases are shown. It is found that tendencies of the dependence of (normalized) real frequency on α and εT in the ITER and CFETR cases are similar with those in the CBC case; for a fixed (kθρs, D, α, εT), the (normalized) real frequency in three cases are of the same order. Tendencies of the dependence of (normalized) growth rate in the ITER case on α and εT are similar with those in the CBC case, except that the magnitude is about 30% smaller. The magnitude of growth rate in the CFETR case is close to that in the CBC case in a large range of α and εT, however, the tendency is not quite similar. It is seen that by varying εT from 0.0 to 0.5, the growth rate in the CFETR case is nearly unchanged when α = 1/2, and only about 20% increment when α = 1 and 2 in large kθρs, D region. Analogously, dependence of the growth rate on α is not quite obvious. When α varies from 1/2 to 2, the increment of the growth rate in the CFETR case is about 50%, which is much smaller than the increments in the CBC and ITER cases. These results show that the ITG instability is the weakest in the ITER case, and is least affected by varying α and εT in the CFETR case.
To end this section, we make some remarks on the results about the linear frequency. In our modelling, only the temperature anisotropy of D is considered; effects of the anisotropy factor αD and the fraction of T εT on the linear frequency depend on this assumption. Obviously, when the temperature anisotropy of T is also considered, the situation becomes complicated. For example, in the case with εT increased, though the influence of temperature anisotropy from D decreases, the influence of temperature anisotropy from T increases, and the final results depend on the competition of the temperature anisotropy between D and T. In this work, we do not focus on the analysis of this complicated situation, but emphasize the significant role of the temperature anisotropy on the linear frequency in a relatively easy way.
In this section, based on the linear results in section 3, a quasilinear transport model is adopted to study the effects of temperature anisotropy on the particle and energy fluxes driven by the ITG instability.
We begin with the relation between the driven fluxes and the driving forces [21, 29–31]
\mathcal{J}_\eta=L_{\eta \nu} \mathcal{X}^\nu . | (10) |
Here, η, ν = 1, 2, 3, 4, 5, Lην is the transport coefficient, which can be explicitly written in the quasilinear theory framework as [32, 33]
(11) |
It associates with the velocity integral for the weighting factors hη(ν) and the linear frequency. Obviously, Lην satisfies the Onsager symmetry [29, 30] automatically.
The particle and energy fluxes are generally defined as
\Gamma^r \equiv \int \mathrm{d}^3 \boldsymbol{v}\left\langle\delta v_r \delta f\right\rangle_{\varepsilon}, | (12a) |
Q^r \equiv \int \mathrm{d}^3 v \frac{1}{2} m v^2\left\langle\delta v_r \delta f\right\rangle_{\varepsilon}. | (12b) |
Here, δf is the perturbed particle distribution function with the Fourier component shown in equation (5). δvr is the radial component of the perturbed E × B drift. \langle\cdot\rangle_{\varepsilon} denotes the ensemble average, which is usually defined as the average over the periodic poloidal and toroidal angle, and average over the time. Note that the phase difference between δvr and the polarization part in δf is π/2, only the gyrocenter part in δf contributes to the transport fluxes. By substituting equation (5) into equations (12a) and (12b), and by combining the definitions in equations (10) and (11), it is easy to find
\frac{1}{n_0} \Gamma^r=\mathcal{J}_1, | (13a) |
\frac{1}{n_0 T_{\perp}} Q^r=\left(1+\frac{1}{2 \alpha}\right) \mathcal{J}_1+\mathcal{J}_2+\frac{1}{\alpha} \mathcal{J}_3, | (13b) |
from which we can define the heat flux
\frac{1}{n_0 T_{\perp}} q^r=\mathcal{J}_2+\frac{1}{\alpha} \mathcal{J}_3 . | (13c) |
Further analyses show that \mathcal{J}_2=q_{\perp}^r / T_{\perp}, which denotes the perpendicular heat flux, \mathcal{J}_3=q_{\|}^r / T_{\|}, which denotes the parallel heat flux. Note that in the above derivation, we omit the label 'j' to treat D and T equally. In the following part, we use Γr/n0 and Qr/n0T⊥(qr/n0T⊥ ) to describe the transport level for particle and energy (heat).
In the quasilinear transport theory, the mixing length model approximation [32, 34, 35] is widely used to quantitatively analyze the turbulent transport fluxes. It reads as
(14) |
then the transport coefficients can be rewritten as
L_{\eta \nu}=\int_0^{\infty} \mathrm{d} \mathcal{E} \frac{\left\langle h_\eta h_\nu\right\rangle_{\hat{\hat{v}_‖}}}{\left(\hat{\omega}_{\mathrm{r}}-2 \mathcal{E}\right)^2+\hat{\gamma}^2} \frac{\hat{\gamma}^3}{k_\theta \rho_{\mathrm{s}, \mathrm{D}}} \frac{a}{R} \chi_{\mathrm{GB}} . | (15) |
Here, \langle\cdot\rangle_{\hat{v_{\|}}} denotes the -integral. and denote the real frequency and growth rate normalized by ω0D, respectively. χGB, defined as , is usually used to normalize the transport coefficients. According to the parameters shown in table 1, χGB is evaluated to be 5.83 m2 s-1 (CBC), 2.57 m2 s-1 (ITER), and 5.05 m2 s-1 (CFETR). Generally, only the spectrum which corresponds to the maximum growth rate should be considered in the calculation of transport coefficients [34], which is relevant to the assumption that the nonlinear transport may be dominated by the mode with the maximum linear growth rate. From figure 3, it is seen that the growth rates with kθρs, D = 0.3–0.5 are comparable in large range of (α, εT); note that the saturation amplitude shown in equation (14) is proportional to , a smaller kθρs corresponds to a larger saturation amplitude for comparable growth rates. Besides, in the CBC case, when only D exists and α = 1, the energy flux is calculated as Q r/nD0T⊥ = 5.49 m s-1 with kθρs, D = 0.4, from which the effective ion heat diffusivity is estimated as χ = 0.27χGB, which agrees well with the GK simulation result [36]. Thus, we take kθρs, D = 0.4 in the following calculation.
Figure 4 shows the particle flux versus εT for D
(16) |
It is seen from figure 4(c) that the total particle flux with different (εT, α) is nearly zero, the absolute value is smaller than 5 × 10-3, the error range we adopted to calculate the left-hand-side of equation (9). Note that in the derivation of equation (9), the adiabatic electron approximation and the quasi-neutrality condition are adopted. Due to the adiabatic approximation, the particle flux for electrons driven by the ITG instability is zero, then the particle flux for ions should also be zero to keep the quasi-neutrality condition. Figure 4(c) is obtained based on the linear frequency and the mixing length model approximation, it proves the accuracy of the linear frequency calculated in section 3 and provides the reliability for the calculation of the quasilinear transport fluxes in section 4.
The particle fluxes for D and T are shown in figures 4(a) and (b), respectively. It is seen that direction of the particle flux for T by varying (α, εT) is opposite to that for D, which qualitatively agrees with equation (16) by noting that the total particle flux is zero. In detail, for a fixed εT, it is shown that
According to the definition in equations (10) and (13a), the particle flux can be divided into three parts: one is driven by the density gradient (L_{11} \mathcal{X}^1), the second is driven by the temperature gradient (L_{12} \mathcal{X}^2+L_{13} \mathcal{X}^3), and the third is due to the inward pinch (L_{14} \mathcal{X}^4+L_{15} \mathcal{X}^5). Totally speaking, as α and εT varied, the linear real frequency and growth rate vary, then the transport coefficients calculated from equation (15) vary, leading to the variation of the contribution from these three parts to the particle flux. The analysis about the contribution from these three parts to the particle flux may be helpful to understand the tendency of the particle flux varied with α and εT. As an example, we take εT = 0.5, α = 1/2, 1 and 2. The values are summarized in table 2. It is shown that with different α, the flux driven by the density gradient is always outward, the flux due to the inward pinch is always inward, the flux driven by the temperature gradient can be inward or outward. For a fixed α, the density gradient parts and the inward pinch parts for D and T are similar, but the temperature gradient parts for D and T are quite different, especially when α = 1/2 and 2. As α increased from 1/2 to 2, the density gradient parts for D and T increase; the inward pinch parts for D and T increase; the temperature gradient part for D(T) changes from inward (outward) to outward (inward), correspondingly, the particle flux for D(T) changes from inward (outward) to outward (inward). The similar results can also be obtained for εT = 0.1 to 0.4. It is indicated that the temperature gradient part plays an important role in determining the direction of particle flux for D and T.
α | L_{11} \mathcal{X}^1 | L_{12} \mathcal{X}^2+L_{13} \mathcal{X}^3 | L_{14} \mathcal{X}^4+L_{15} \mathcal{X}^5 | Total | Direction | |
1/2 | 1.453 | -0.720 | -1.108 | -0.375 | ← | |
D | 1 | 2.543 | -0.117 | -2.261 | 0.166 | → |
2 | 2.987 | 0.795 | -2.900 | 0.882 | → | |
1/2 | 1.365 | 0.324 | -1.315 | 0.374 | → | |
T | 1 | 2.339 | -0.463 | -2.039 | -0.163 | ← |
2 | 2.804 | -1.431 | -2.256 | -0.883 | ← |
Figure 5 shows the particle flux versus εT in the CBC, ITER and CFETR cases. α = 1/2, 1 and 2 are adopted. Totally speaking, tendencies of the particle flux for D and T versus (εT, α) in the ITER and CFETR cases are similar with those in the CBC case. In large range of chosen (εT, α), the particle fluxes for D and T are about 0.5 m s-1, 0.03 m s-1 and 0.2 m s-1 in the CBC, ITER and CFETR cases, respectively, that is, the particle flux is the largest in the CBC case and smallest in the ITER case. These results can be qualitatively explained by combining equation (15) and figure 3. The transport coefficient shown in equation (15) is proportional to γ3 and χGB, both γ and χGB in the ITER case are about half of those in the CBC and CFETR cases, resulting that the particle flux in the ITER case is about an order of magnitude smaller. It is seen that the particle flux in the CFETR case is smaller than that in the CBC case, which is closely related to the contribution from the temperature gradient part and the inward pinch part. We take εT = 0.5 as an example. When α = 2, the particle fluxes for D in the CBC and CFETR case are 0.882 m s-1 and 0.321 m s-1, respectively; however, the temperature gradient parts in the CBC and CFETR case are 0.795 m s-1 and -0.712 m s-1, respectively. The bigger outward particle flux for D in the CBC case is mainly due to the positive contribution from the temperature gradient part. When α = 1/2, the particle fluxes for D in the CBC and CFETR case are -0.375 m s-1 and -0.162 m s-1, respectively; however, the inward pinch parts in the CBC and CFETR case are -1.108 m s-1 and -0.460 m s-1, respectively. The bigger inward particle flux for D in the CBC case is mainly due to the positive contribution from the inward pinch part.
Generally, the inward or smaller outward particle flux means the better particle confinement. In figure 5, it is shown that for a fixed εT, the particle fluxes for both D and T are closer to zero when α approaches to 1 than that when α is far away from 1, indicating that the confinement is better for the isotropic case than that for the anisotropic case. On the other hand, for the anisotropic case, it is found that for a certain α < 1, larger εT (for example, α = 1/2 and εT = 0.5) is beneficial for the particle confinement; for a certain α > 1, smaller εT (for example, α = 2 and εT = 0.1) is beneficial for the particle confinement.
Figure 6 shows the heat and energy fluxes for D versus εT in the CBC case. The heat and energy fluxes are calculated according to equations (13c) and (13b), respectively. It is seen that for a fixed εT, both the heat and energy fluxes increase as α increases, dependences of the heat and energy flux on α are more sensitive in α < 1 region than that in α > 1 region. For εT = 0.5, when α increases from 1/2 to 1, the heat flux increases from about 2.3 to about 4.5 m s-1, the increment is about 96%; when α increases from 1 to 2, the heat flux increases from about 4.5 to about 5.4 m s-1, the increment is about 20%. As shown in equation (13c), the heat flux contains two parts, which are denoted as the perpendicular heat flux (\mathcal{J}_2) and the parallel heat flux (\mathcal{J}_3). A careful analysis shows that the perpendicular part dominates the heat flux (in our cases, the ratios of the parallel part to the total heat flux are 1%, 14% and 20% for α = 1/2, 1 and 2 with εT = 0.5, respectively). Furthermore, the perpendicular heat flux is dominated by the temperature gradient part (L_{22} \mathcal{X}^2+L_{23} \mathcal{X}^3). It is found that dependence of the heat flux on α has the similar tendency to that of the temperature gradient part.
As shown in equation (13b), the energy flux contains the particle flux and the heat flux. According to figures 4(a) and 6(a), the particle flux is much smaller than the heat flux, thus the heat flux dominates the energy flux. It is seen that dependence of the energy flux on α is similar to that of the heat flux. In addition, for a fixed α, dependence of the heat flux on εT is just opposite to that of the particle flux, which leads to that the energy flux moderately decreased as εT increases. When εT varies from 0.1 to 0.5, the biggest change of energy flux occurs at α = 1, which is dropped from about 5.3 to about 4.7 m s-1. It indicates that the energy transport can be significantly reduced in the situation where the parallel temperature dominates (α < 1), and effectively aggravated in the situation where the perpendicular temperature dominates (α > 1).
Figure 7 shows the heat and energy fluxes for T versus εT in the CBC case. It is seen that dependence of the heat flux for T on (α, εT) and its value are similar to those for D. The heat flux for T increases as α increases, and the increment is more significant in α < 1 region. Analogously, the perpendicular heat flux dominates the heat flux, and the temperature gradient part dominates the perpendicular heat flux. Unlike the situation for the heat flux, dependence of the energy flux on (α, εT) shows different characters. Since the particle flux for T is comparable to the heat flux for T, due to the modulation of particle flux, the energy flux is not sensitive to εT, and its value obviously increases (decreases) in α < 1 (α > 1) region, where the particle flux is outward (inward). It is seen that the biggest energy flux appears at α = 1. When α is far away from α = 1, the energy flux for T can be moderately suppressed by about 20%–40% in the chosen parameter ranges.
Figure 8 shows the energy flux versus εT in the CBC, ITER and CFETR cases. α = 1/2, 1 and 2 are adopted. Tendencies of the energy flux for D and T versus (εT, α) in the ITER and CFETR cases are similar with those in the CBC case. In each case, qualitatively, dependence of the energy flux for D on α is more significant than that for T, dependences of the energy flux for both D and T on εT are not obvious, which are due to the modulation of the particle flux, as illustrated in the following figures 6 and 7. Quantitatively, analogous to the particle flux shown in figure 5, the energy flux in the ITER case is an order of magnitude smaller than that in the CBC case, which is due to the smaller growth rate and χGB, as is discussed following figure 5. The energy flux in the CFETR case is about half of magnitude smaller than that in the CBC case. Note that the energy flux can also be divided into three parts, which are driven by the density gradient, the temperature gradient and the inward pinch. As an example, in table 3, we show the contribution from these three parts to the energy flux for D with εT = 0.5 and α = 1/2, 1 and 2. It is shown that in the CBC case, the density gradient part and the inward pinch are mostly cancelled, the value of the total energy flux is close to that of the temperature gradient part. In the CFETR case, values of these three parts are smaller than those in the CBC case. Though the transport coefficients described by equation (15) are close in CBC and CFETR cases, the fluxes are not close, since the the fluxes are calculated by the product of transport coefficients and driving forces (\mathcal{X}^\nu). For example, in our modelling, \mathcal{X}^2=\mathcal{X}^3=\kappa_{\mathrm{T}} / R, the bigger R results in the smaller energy flux in the CFETR case.
α | Density gradient | Temperature gradient | Inward pinch | Total | |
1/2 | 2.473 | 1.418 | -2.331 | 1.560 | |
CBC | 1 | 3.777 | 5.208 | -4.287 | 4.699 |
2 | 3.867 | 7.441 | -4.825 | 6.483 | |
1/2 | 1.807 | 0.320 | -0.908 | 1.220 | |
CFETR | 1 | 2.205 | 1.372 | -1.294 | 2.283 |
2 | 2.109 | 1.911 | -1.339 | 2.681 |
Besides, it is seen that the optimal confinement for the energy of D and T appears at α = 1/2, regardless of the value of εT.
In conclusion, the particle and energy transports driven by the ITG instability are investigated in an anisotropic D-T plasma.
At first, the linear dispersion relation is derived in the local kinetic limit. Three sets of typical parameters, denoted as CBC, ITER and CFETR case, respectively, are chosen to numerically solve the dispersion relation. Dependences of the linear mode frequency on parameters, such as the temperature anisotropy factor of D α, the fraction of T particle εT and the poloidal spectrum kθρs, D, are studied. Based on the linear results, the quasilinear transport coefficients are derived by adopting the mixing length model approximation, and the particle and energy fluxes for D and T are evaluated.
The main results are concluded as follows:
(1) Dependences of the linear frequency and the quasilinear transports on the parameters in the three cases show the similar tendency. Values of the real frequency in the three cases are nearly the same, the growth rate is the smallest in the ITER case, and largest in the CBC case. The quasilinear particle and energy transports are the largest in the CBC case and the smallest in the ITER case, which indicates the better particle and energy confinement in large devices.
(2) As α increases, the real frequency decreases, while the growth rate increases; in α > 1 (α < 1) region, the real frequency increases (decreases) as εT increases, while the growth rate decreases (increases). The ITG instability may be significantly stabilized by controlling α < 1.
(3) Due to the adiabatic electron approximation and the quasi-neutrality condition, the total particle flux for ions is found to be zero; this result proves the accuracy for the calculation of the linear frequency and provides the reliability for the calculation of the quasilinear transport fluxes. The direction of the particle flux for D is opposite to that of T; the temperature gradient driven particle flux plays an important role in determining the direction of the particle flux for D and T. It is shown that the particle confinement is better for the isotropic case than that for the anisotropic case when εT is fixed. On the other hand, for the anisotropic case, it is found that for a certain α < 1 (α > 1), larger εT (smaller εT) is beneficial for the particle confinement.
(4) As α increases, the heat fluxes for D and T increase, the increment is more sensitive in α < 1 region than that in α > 1 region. Due to the modification of the particle flux, dependences of the energy flux for D and T on α show different tendencies. As α increases, the energy flux for D increases, while the energy flux for T increases in α < 1 region and then decreases in α > 1 region. The largest energy flux for T appears at α = 1; as the deviation of α is larger from 1, the energy flux becomes smaller. It is concluded that smaller α is beneficial for energy confinement.
(5) Totally speaking, in the ITG-dominated regime, the better particle and energy confinement occur by choosing smaller α and larger εT.
To the end, it should be pointed out that a significant source of anisotropy in high performance machines is NBI, which may also produce a sheared flow in the plasma. Consideration of the consistency between temperature anisotropy and sheared flows may be helpful for a better estimation of turbulent transport level in devices such as ITER and CFETR. This issue will be left as a future work.
In this appendix, we give a brief derivation of the perturbed distribution function shown in equation (3) based on the traditional GK theory [18].
In terms of the gyrocenter (GY, following the terminology of [18], we denote the guiding center (GC) in perturbed fields as gyrocenters) coordinates
(A.1) |
where
(A.2) |
where
\dot{\boldsymbol{X}}_0=\bar{v}_{\|} \frac{B^*}{B_{\|}^*}+\frac{1}{e B_{\|}^*} \boldsymbol{b} \times \bar{\mu} \nabla B, | (1.3a) |
\dot{\overline{\boldsymbol{X}}}_1=\frac{\boldsymbol{b} \times \nabla\langle\delta \phi\rangle}{B_{\|}^*} \text {. } | (1.3b) |
(1.4a) |
\dot{\bar{v}}_{\|, 1}=-\frac{e \boldsymbol{B}^*}{m B_{\|}^*} \cdot \nabla\langle\delta \phi\rangle . | (1.4b) |
Here, the subscript '0' and '1' denote the unperturbed and perturbed quantities, respectively. \langle\delta \phi\rangle denotes the gyro-average of δϕ. with .
By introducing the coordinate transformation
(1.5) |
By using the identities and \dot{\bar{X}}_1 \cdot \bar{\mu} \nabla B+m \bar{v}_{\|} \dot{\bar{v}}_{\|, 1}=-\dot{\boldsymbol{\bar{X}}}_0 \cdot e \nabla\langle\delta \phi\rangle, equation (1.5) can be reduced as
\partial_t \bar{F}_1+\dot{\overline{\boldsymbol{X}}}_0 \cdot \nabla \bar{F}_1=-\dot{\overline{\boldsymbol{X}}}_1 \cdot \nabla \bar{F}_0+\dot{\overline{\boldsymbol{X}}}_0 \cdot e \nabla\langle\delta \phi\rangle \partial_E \bar{F}_0. | (1.6) |
We further introduce the adiabatic transformation \bar{F}_1=\bar{H}_1+e\langle\delta \phi\rangle \partial_E \bar{F}_0, where denotes the non-adiabatic part of the perturbed distribution function, then (1.6) can be transformed to be
\partial_t \bar{H}_1+\dot{\overline{\boldsymbol{X}}}_0 \cdot \nabla \bar{H}_1=-\partial_t e\langle\delta \phi\rangle \partial_E \bar{F}_0-\dot{\overline{\boldsymbol{X}}}_1 \cdot \nabla \bar{F}_0 . | (1.7) |
We then solve equation (1.7) in the Fourier space. Note that equation (1) shows the Fourier transformation for a function with respect to the particle position r. We introduce the GC coordinates Z = ( X, v‖,μ, ξ ), where X, v‖,μ and ξ denote the GC position, parallel velocity, magnetic moment and gyro-angle, respectively. By using r = X + ρ(μ, ξ ), where ρ is the gyro-radius, equation (1) can be rewritten in the GC coordinates as
(1.8) |
where Jn is the nth order Bessel function with argument λ = k⊥ ρ. In the GK theory, the perturbed quantities shown in equation (1.7) are directly evaluated at
(1.9) |
where J0 originates from the gyro-average of δϕ. Note that the parallel dynamics has been neglected for simplicity.
In the GK theory, the GC distribution function F(
Z) can be obtained from the GY distribution function
(1.10) |
Here, G1's denote the generating vector fields, which are explicitly expressed as [18, 33]
(1.11a) |
(1.11b) |
(1.11c) |
Here, S1 is the 1st order gauge function, which is calculated as
\begin{aligned} S_1 & =\int \mathrm{d} \widetilde{\xi \delta}, \\ & =e \sum_k \phi_k \mathrm{e}^{\mathrm{i}(k \cdot X-\omega t)} \sum_{n \neq 0} \frac{1}{\mathrm{i} n \Omega} J_n \mathrm{e}^{\mathrm{i} n \xi}, \end{aligned} | (1.12) |
where \widetilde{\delta \phi}=(\delta \phi-\langle\delta \phi\rangle). Then the generating vector fields are calculated as
(1.13a) |
(1.13b) |
(1.13c) |
(1.13d) |
The particle distribution function f(r) can be obtained from the GC distribution function F(X) by noting the transformation X = r - ρ, namely, f(r) = F(r - ρ) = e-iρ·∇F(r). By using the identities
the gyro-averaged particle distribution function can be obtained according to equations (1.9)–(1.13d) as
\begin{aligned} \left\langle f_{\boldsymbol{k}}\right\rangle= & e \phi_{\boldsymbol{k}}\left(1-J_0^2\right)\left(\partial_E \bar{F}_0+\frac{1}{B} \partial_\mu \bar{F}_0\right) \\ & +e \phi_{\boldsymbol{k}} J_0^2\left(\frac{-\omega_{\mathrm{d}} \partial_E \bar{F}_0+\frac{1}{e B} \boldsymbol{b} \times \boldsymbol{k} \cdot \nabla \bar{F}_0}{\omega-\omega_{\mathrm{d}}}\right), \end{aligned} | (1.14) |
which agrees with equation (3). We mention that the key points in the derivation are (i) the derivation of the linear GK equation and (ii) the transformation among the particle, GC and GY distribution functions.
This work was supported by the National MCF Energy R&D Program of China (No. 2019YFE03060000), and National Natural Science Foundation of China (Nos. 12005063, 12175228, 11875131 and 11675053).
[1] |
Groebner R J et al 1986 Nucl. Fusion 26 543 doi: 10.1088/0029-5515/26/5/001
|
[2] |
Scott S D et al 1990 Phys. Rev. Lett. 64 531 doi: 10.1103/PhysRevLett.64.531
|
[3] |
Xu X Q and Rosenbluth M N 1991 Phys. Fluids B 3 627 doi: 10.1063/1.859862
|
[4] |
Hole M J et al 2011 Plasma Phys. Control. Fusion 53 074021 doi: 10.1088/0741-3335/53/7/074021
|
[5] |
Huang J et al 2017 Plasma Phys. Control. Fusion 59 065010 doi: 10.1088/1361-6587/aa6988
|
[6] |
Jia M X et al 2021 Nucl. Fusion 61 046033 doi: 10.1088/1741-4326/abe6b5
|
[7] |
Berkery J W et al 2014 Phys. Plasmas 21 112505 doi: 10.1063/1.4901568
|
[8] |
Chen H T and Chen L 2021 Phys. Plasmas 28 052103 doi: 10.1063/5.0044910
|
[9] |
Ren H J and Cao J T 2014 Phys. Plasmas 21 122512 doi: 10.1063/1.4903911
|
[10] |
Ren H J 2017 Plasma Sci. Technol. 19 122001 doi: 10.1088/2058-6272/aa936f
|
[11] |
Ming Y, Zhou D and Wang W J 2018 Plasma Sci. Technol. 20 085101 doi: 10.1088/2058-6272/aabc5c
|
[12] |
Ren H J 2016 Phys. Plasmas 23 064507 doi: 10.1063/1.4954914
|
[13] |
Cho Y W and Hahm T S 2021 Phys. Plasmas 28 052303 doi: 10.1063/5.0050824
|
[14] |
Strugarek A et al 2013 Phys. Rev. Lett. 111 145001 doi: 10.1103/PhysRevLett.111.145001
|
[15] |
Calvo I et al 2020 Nucl. Fusion 60 016035 doi: 10.1088/1741-4326/ab581f
|
[16] |
Rutherford P H and Frieman E A 1968 Phys. Fluids 11 569 doi: 10.1063/1.1691954
|
[17] |
Frieman E A and Chen L 1982 Phys. Fluids 25 502 doi: 10.1063/1.863762
|
[18] |
Brizard A J and Hahm T S 2007 Rev. Mod. Phys. 79 421 doi: 10.1103/RevModPhys.79.421
|
[19] |
Romanelli F 1989 Phys. Fluids B 1 1018 doi: 10.1063/1.859023
|
[20] |
Ren H J 2015 Phys. Plasmas 22 072502 doi: 10.1063/1.4923383
|
[21] |
Wang S J 2016 Phys. Plasmas 23 072509 doi: 10.1063/1.4959812
|
[22] |
Zhang D B, Xu Y F and Wang S J 2017 Phys. Plasmas 24 030701 doi: 10.1063/1.4977808
|
[23] |
Terry P, Anderson W and Horton W 1982 Nucl. Fusion 22 487 doi: 10.1088/0029-5515/22/4/004
|
[24] |
Dimits A M et al 2000 Phys. Plasmas 7 969 doi: 10.1063/1.873896
|
[25] |
Angioni C and Peeters A G 2008 Phys. Plasmas 15 052307 doi: 10.1063/1.2913610
|
[26] |
Shi N et al 2017 Nucl. Fusion 57 126046 doi: 10.1088/1741-4326/aa79d1
|
[27] |
Ye L et al 2016 J. Comput. Phys. 316 180 doi: 10.1016/j.jcp.2016.03.068
|
[28] |
Dong J Q, Horton W and Kim J Y 1992 Phys. Fluids B 4 1867 doi: 10.1063/1.860040
|
[29] |
Onsager L 1931 Phys. Rev. 37 405 doi: 10.1103/PhysRev.37.405
|
[30] |
Onsager L 1931 Phys. Rev. 38 2265 doi: 10.1103/PhysRev.38.2265
|
[31] |
Angioni C et al 2012 Nucl. Fusion 52 114003 doi: 10.1088/0029-5515/52/11/114003
|
[32] |
Nordman H and Weiland J 1989 Nucl. Fusion 29 251 doi: 10.1088/0029-5515/29/2/008
|
[33] |
Wang S J 2012 Phys. Plasmas 19 062504 doi: 10.1063/1.4729660
|
[34] |
Connor J W and Pogutse O P 2001 Plasma Phys. Control. Fusion 43 155 doi: 10.1088/0741-3335/43/2/306
|
[35] |
Balesc R 2005 Aspects of Anomalous Transport in Plasmas (Bristol: Institute of Physics Publishing)
|
[36] |
Xu Y F et al 2017 Phys. Plasmas 24 082515 doi: 10.1063/1.4986395
|
[37] |
Cary J R 1981 Phys. Rep. 79 129 doi: 10.1016/0370-1573(81)90175-7
|
[38] |
Cary J R and Littlejohn R G 1983 Ann. Phys. 151 1 doi: 10.1016/0003-4916(83)90313-5
|
[1] | Yifei LIU, Jiquan LI. Gyro-Landau-fluid simulations of impurity effects on ion temperature gradient driven turbulence transport[J]. Plasma Science and Technology, 2024, 26(1): 015101. DOI: 10.1088/2058-6272/ad0c9b |
[2] | Ting WU (吴婷), Lin NIE (聂林), Min XU (许敏), Jie YANG (阳杰), Zhipeng CHEN (陈志鹏), Yuejiang SHI (石跃江), Nengchao WANG (王能超), Da LI (李达), Rui KE (柯锐), Yi YU (余羿), Shaobo GONG (龚少博), Ting LONG (龙婷), Yihang CHEN (陈逸航), Bing LIU (刘兵), J-TEXT Team. Effect of resonant magnetic perturbation on boundary plasma turbulence and transport on J-TEXT tokamak[J]. Plasma Science and Technology, 2019, 21(12): 125102. DOI: 10.1088/2058-6272/ab4369 |
[3] | WANG Chunlin (王春林), WU Yi (吴翊), CHEN Zhexin (陈喆歆), YANG Fei (杨飞), FENG Ying (冯英), RONG Mingzhe (荣命哲), ZHANG Hantian (张含天). Thermodynamic and Transport Properties of Real Air Plasma in Wide Range of Temperature and Pressure[J]. Plasma Science and Technology, 2016, 18(7): 732-739. DOI: 10.1088/1009-0630/18/7/06 |
[4] | LIU Hai (刘海), CHEN Zhipeng (陈志鹏), ZHUANG Ge (庄革), SUN Yue (孙岳), ZHU Lizhi (朱立志), XIAO Chijin (肖持进), CHEN Jie (陈杰). Investigation of the Ion Energy Transport in the Scrape-Off Layer on the J-TEXT Tokamak Using a Retarding Field Analyzer[J]. Plasma Science and Technology, 2016, 18(6): 601-606. DOI: 10.1088/1009-0630/18/6/04 |
[5] | ZHOU Xue (周学), CUI Xinglei (崔行磊), CHEN Mo (陈默), ZHAI Guofu (翟国富). Thermodynamic Properties and Transport Coefficients of Nitrogen, Hydrogen and Helium Plasma Mixed with Silver Vapor[J]. Plasma Science and Technology, 2016, 18(5): 560-568. DOI: 10.1088/1009-0630/18/5/20 |
[6] | CAO Lihua(曹莉华), WANG Huan(王欢), ZHANG Hua(张华), LIU Zhanjun(刘占军), WU Junfeng(吴俊峰), LI Baiwen(李百文). Two-Dimensional Hybrid Model for High-Current Electron Beam Transport in a Dense Plasma[J]. Plasma Science and Technology, 2014, 16(11): 1007-1012. DOI: 10.1088/1009-0630/16/11/03 |
[7] | WANG Fuqiong(王福琼), CHEN Yiping(陈一平), HU Liqun(胡立群). DIVIMP Modeling of Impurity Transport in EAST[J]. Plasma Science and Technology, 2014, 16(7): 642-649. DOI: 10.1088/1009-0630/16/7/03 |
[8] | LIN Zhihong (林志宏), S. ETHIER, T. S. HAHM, W. M. TANG. Verification of Gyrokinetic Particle Simulation of Device Size Scaling of Turbulent Transport[J]. Plasma Science and Technology, 2012, 14(12): 1125-1126. DOI: 10.1088/1009-0630/14/12/17 |
[9] | SUN Yue (孙岳), CHEN Zhipeng (陈志鹏), WANG Zhijiang (王之江), ZHU Mengzhou (朱孟周), ZHUANG Ge (庄革), J-TEXT team. Experimental Studies of Electrostatic Fluctuations and Turbulent Transport in the Boundary of J-TEXT Tokamak Using Reciprocating Probe[J]. Plasma Science and Technology, 2012, 14(12): 1041-1047. DOI: 10.1088/1009-0630/14/12/02 |
[10] | CHEN Ling (陈玲), WU Dejin (吴德金). Dispersion Equation of Low-Frequency Waves Driven by Temperature Anisotropy[J]. Plasma Science and Technology, 2012, 14(10): 880-885. DOI: 10.1088/1009-0630/14/10/05 |
1. | Tang, R., Zhang, D., Zhang, X. et al. Gyrokinetic simulations of ion temperature gradient instability in deuterium-tritium plasma in the CFETR hybrid scenario. AIP Advances, 2023, 13(9): 095312. DOI:10.1063/5.0155150 |
2. | Yang, Y., Liu, M., Zhou, C. et al. Effects of the energetic particles on the anomalous transport driven by the ion temperature gradient instability. Physics of Plasmas, 2022, 29(8): 082503. DOI:10.1063/5.0097944 |
Case | R0 (m) | a (m) | B0 (T) | T⊥ (keV) | κn | κT |
CBC | 1.67 | 0.6 | 1.9 | 1.97 | 2.23 | 6.96 |
ITER | 6.2 | 2.0 | 5.3 | 10.0 | 3.0 | 6.0 |
CFETR | 5.7 | 1.6 | 5.0 | 12.5 | 3.93 | 8.91 |
α | L_{11} \mathcal{X}^1 | L_{12} \mathcal{X}^2+L_{13} \mathcal{X}^3 | L_{14} \mathcal{X}^4+L_{15} \mathcal{X}^5 | Total | Direction | |
1/2 | 1.453 | -0.720 | -1.108 | -0.375 | ← | |
D | 1 | 2.543 | -0.117 | -2.261 | 0.166 | → |
2 | 2.987 | 0.795 | -2.900 | 0.882 | → | |
1/2 | 1.365 | 0.324 | -1.315 | 0.374 | → | |
T | 1 | 2.339 | -0.463 | -2.039 | -0.163 | ← |
2 | 2.804 | -1.431 | -2.256 | -0.883 | ← |
α | Density gradient | Temperature gradient | Inward pinch | Total | |
1/2 | 2.473 | 1.418 | -2.331 | 1.560 | |
CBC | 1 | 3.777 | 5.208 | -4.287 | 4.699 |
2 | 3.867 | 7.441 | -4.825 | 6.483 | |
1/2 | 1.807 | 0.320 | -0.908 | 1.220 | |
CFETR | 1 | 2.205 | 1.372 | -1.294 | 2.283 |
2 | 2.109 | 1.911 | -1.339 | 2.681 |