
Citation: | Jing OU, Jiamin LONG. Estimates of required impurity fraction for EAST divertor detachment[J]. Plasma Science and Technology, 2025, 27(1): 015103. DOI: 10.1088/2058-6272/ad8ffb |
During the EAST radiative divertor experiments, one of the key challenges was how to avoid the occurrence of disruptive events caused by excessive impurity seeding. To estimate the required impurity fraction for divertor detachment, we introduce a reduced edge plasma radiation model. In the model, based on the momentum conservation along the magnetic field line, the upstream pressure is determined by the plasma density and temperature at the divertor target, and then the impurity radiation loss is obtained by the balance of the heat and particle fluxes. It is found that the required impurity fraction shows a non-monotonic variation with divertor electron temperature (Td) when 0.1eV<Td<10eV. In the range of 0.1eV<Td<1eV, the position near the valley of required impurity fraction corresponds to strong plasma recombination. Due to the dependence of the volumetric momentum loss effect on the Td in the range of 1eV<Td<10eV, the required impurity fraction peaks and then decreases as Td is increased. Compared to neon, the usage of argon reduces the impurity fraction by about twice. In addition, for the various fitting parameters in the pressure–momentum loss model, it is shown that the tendency of required impurity fraction with Td always increases first and then decreases in the range of 1eV<Td<10eV, but the required impurity fraction decreases when the model that characterizes the strong loss in pressure momentum is used.
The macroscale magnetohydrodynamic (MHD) instabilities have been continually concerned to ensure steady-state operation in tokamak plasmas [1–10]. The neoclassical tearing mode (NTM), one kind of MHD instabilities driven by the loss of bootstrap current inside the seeded magnetic islands, can greatly degrade the confinement and even lead to major disruptions [11–20]. In the [13], it is indicated that (2, 1) NTM is potentially the most serious one as it always results in severe energy confinement degradation and can lead to disruptions. It is therefore significant to determine the scaling behavior for the (2, 1) mode of NTMs in tokamak [4, 12, 13]. On the other hand, the NTM has been observed in many experiment devices such as TFTR [14], ASDEX Upgrade [21] and DIII-D [22]. These experiments have demonstrated that the NTM can affect the heat transport and equilibrium of plasma, reducing the confinement time of plasma energy in the nuclear fusion, which is extremely detrimental during the discharge [13, 14, 21–23]. In short, the NTM is greatly prone to being produced and results in deleterious consequences.
During tokamak discharge, plasma radiation is one of the most crucial mechanisms of plasma energy loss, and plays significant roles in the development of MHD instabilities [24, 25]. In general, there are three principal types of radiation, namely the bremsstrahlung radiation, the electron cyclotron radiation and the impurity radiation [26–28]. In the experiments, furthermore, the radial and poloidal evolutions of the impurity radiation are observed in JET. Then the mechanism on how the impurity radiation influences the MHD instabilities has been attempted [26]. It is worth emphasizing that the heat flux generated by the auxiliary heating from the core plasmas is shielded by the magnetic islands, such that the heat flux of the auxiliary heating only flows outside the magnetic islands along the X-point [27]. Consequently, the energy in the magnetic islands primarily depends on the Ohmic heating and the radiation cooling. In particular, some disruptions are the result of the plasma radiation, and hence the explorations on disruptions have been carried out [28, 29]. Suttrop et al observed the current contraction phase beginning with the growth of (3, 1) islands due to the cooling effect of the carbon impurity radiation at the high-q density limit in ASDEX Upgrade [30]. Teng et al studied the thermal perturbations inside and outside magnetic islands and found that the large magnetic islands at the density limit can be induced by the impurity radiation [31, 32]. However, it should be mentioned that the electron cyclotron radiation is not taken into account in the work of Teng et al [32]. Perkins and Hulse analytically investigated the effect of the ratio of the radiated power to the Ohmic heating [33]. The density limit disruptions caused by the impurity radiation are practically coincident with the current decay at the safety factor
In this work, we study the radiation effects during the nonlinear evolution of NTMs with different bootstrap current proportions by using a reduced MHD model. It is clearly demonstrated that with increasing the plasma radiation, the pressure is reduced and then perturbation of pressure near the rational surface is increased. At the same time, the radiation can increase the width of magnetic islands and furthermore greatly destroy the quasi-steady-state of tokamak operation. In section 2, the modeling equations are introduced. The results of numerical simulations are presented and the relevant physical mechanisms are discussed in section 3.1. Furthermore, section 3.2 shows the effects of the ratio of transport coefficients
The nonlinear evolution of the NTMs with the existence of radiation, is investigated by reduced MHD equations in the cylindrical geometry
(1) |
(2) |
(3) |
where
(4) |
Each variable in equations (1)‒(3) can be written similar to
(5) |
with
In the last term in equation (3)
(6) |
(7) |
where
It can be measured that certain kinds of impurities are produced in tokamak edge during the discharge. Impurity radiation is one of the main energy sources of the radiation cooling and mainly originated from the magnetic islands [26]. Obviously, the impurity accumulation at O-point of the magnetic islands is the maximal, while it is the minimal at the boundary. Thus, it is assumed that the impurity is Gaussian distribution in the magnetic islands [24]:
(8) |
where
(9) |
where
Equations (1)‒(3) can be solved by an initial value code: MDC (MHD @ Dalian Code) [11, 15–19]. The two-step predictor-corrector method is applied in the time advancement. To solve these equations (1)‒(3), two different methods are used in different directions. In the radial direction, the finite difference method is employed, while the pseudo-spectral method is used for the poloidal and the toroidal directions. The initial pressure and safety factor
and the plasma rotation is considered by setting
where
Up to now, it has been planned to choose tungsten as the upper and lower divertor materials of EAST [37, 38]. In the future tokamak, moreover, tungsten will be selected as the first wall material in ITER [39], and then tungsten impurities must inevitably be produced during the sputtering process. Therefore, tungsten is necessarily studied as the source of the impurity radiation in this work.
In this section, the effects of the plasma radiation on the NTMs are discussed. Particularly, tungsten is chosen as the main source of the impurity radiation and we take
The typical contour plots of the plasma pressure with and without radiation are shown in figure 3. It can be observed that, in the presence of radiation, the pressure reduces drastically inside the magnetic islands and presents a concave structure, which can be observed obviously at
The eigenmode structures of
The temporal evolution of the magnetic island width of different
The above numerical simulation results show that the plasma radiation can destabilize the NTMs. In addition, such a result can be further explained by the theoretical analysis. White et al modified the Rutherford equation comprehensively in [40]:
(10) |
where
(11) |
where
This section presents the influence of the heat transport coefficients on the NTMs with the plasma radiation. There is no doubt that the energy confinement time in tokamak is inversely proportional to the heat transport coefficients, so it is significantly important in the field of magnetic confinement to further understand the physical mechanism of the heat transport coefficients in the presence of the plasma radiation. It can be found that the growth rate of the magnetic islands decreases with the decline of the ratio
The numerical results reported in this work reveal the effects of the radiation on the NTMs, based on a set of reduced MHD equations. The main results can be summarized as follows. First of all, the plasma radiation can reduce the pressure near the rational surface, resulting in the increase of the perturbation of pressure inside the magnetic islands, such that the plasma pressure forms a concave structure. Particularly, the effects of radiation can lead to the increase of the perturbation of bootstrap current inside the magnetic islands, so that the magnetic islands do not saturate and keep growing. In addition, the perturbation of pressure can also be enhanced and then the magnetic islands are destabilized by increasing the ratio of
This work was supported by National Natural Science Foundation of China (No. 12375227) and Innovation in Fusion Engineering Technology of Institute (No. E35QT1080C).
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