The thermal collapse of a nearly collisionless plasma interacting with a cooling spot, in which the electron parallel heat flux plays an essential role, is both theoretically and numerically investigated. We show that such thermal collapse, which is known as thermal quench in tokamaks, comes about in the form of propagating fronts, originating from the cooling spot, along magnetic field lines. The slow fronts, propagating with local ion sound speed, limit the aggressive cooling of plasma, which is accompanied by a plasma cooling flow toward the cooling spot. The extraordinary physics underlying such a cooling flow is that the fundamental constraint of ambipolar transport along the field line limits the spatial gradient of electron thermal conduction flux to the much weaker convective scaling, as opposed to the free-streaming scaling, so that a large electron temperature and, hence, pressure gradient can be sustained. The last ion front for a radiative cooling spot is a shock front where cold but flowing ions meet hot ions.

When magnetic field lines suddenly intercept solid surfaces that provide a sink for plasma energy and sometimes particles, a magnetized fusion-grade plasma can undergo a thermal collapse. This can happen, for example, in the thermal quench (TQ) of fusion plasma during either naturally occurring or intentionally triggered, mitigated tokamak disruptions. The naturally occurring tokamak disruption can be triggered when large-scale MHD activities turn nested flux surfaces into globally stochastic field lines that connect fusion-grade core plasma directly to the divertor/first wall.1–4 As a result, the substantial thermal energy of plasmas is released within a few milliseconds,5–7 causing severe damage to plasma facing components8 (PFCs). Major disruptions are also intentionally triggered for disruption mitigation by injecting high-Z impurities, for example, in the form of deliberately injected solid pellets.9–12 The injected high-Z impurities into a pre-disruption plasma are intended to have the hot plasma deposit its thermal energy onto the pellet, so pellet materials can be ablated and ionized to be assimilated within the flux surface. The ablated pellet materials, thus, initially form radiative cooling mass (RCM) that provides strongly localized radiative cooling for the thermal energy of the surrounding fusion-grade plasma. The fact that the background plasma undergoes a thermal quench by transporting energy into the RCM, which through radiation can spread the heat load over the entire first wall, is the logic behind this approach for thermal quench mitigation. In both situations, the plasma will attach to an energy sink, being a vapor-shielded wall or the ablated pellet, and lose its energy via the fast parallel transport to the energy sink. It must be emphasized that for fusion-grade plasmas, which are nearly collisionless provided that the plasma mean-free-path, λ mfp 10 km, is much longer than the magnetic connection length LB or the tokamak major radius, the TQ due to the presence of a cooling spot (energy sink) is in an exotic kinetic regime, in which the fast parallel transport along the field lines is expected to be the dominant mechanism. The normal expectation is that such nearly collisionless parallel transport of plasma thermal energy in the short magnetic connection length regime represents a worst-case scenario of a TQ in tokamaks, where the plasma thermal energy is released in the shortest possible time. Therefore, understanding the plasma TQ in such an exotic regime is critical for disruption mitigation.

For a nearly collisionless plasma, the prevailing view on the plasma TQ is that the electron thermal conduction flux along the magnetic field line q e plays a dominant role in the heat transport. Instead of following the Braginskii formula,13, q e in the collisionless limit is considered to be constrained by the free-streaming flux limiting14 
(1)
where αe is a numerical factor15  0.1 and v t h , e = T 0 / m e is the electron thermal speed with T0 being surrounding plasma temperature. If the flux-limiting form is straightforwardly applied, then such large q e will suggest a fast TQ occurring at the electron transit time τ t r e = L B / v t h , e. For a fusion-grade plasma with temperature 10 keV, we have τ t r e 2.5 μ s × ( L B / 100 m ), which predicts a remarkably fast TQ for L B < 10 4 m. Such free-streaming form of thermal conduction is believed to dominate over the convective electron energy flux n e V e T e , since ambipolarity constrains V e V i v t h , e and V i are bounded by the ion sound speed cs.

However, it is worth noting that the inhibition of electron thermal conduction in the nearly collisionless plasma has been extensively studied in astrophysics by considering tangled magnetic fields16,17 and plasma instabilities18–20 in order to reach the convection-dominated scenario of the thermal conduction, which would naturally yield the cooling flow that aggregates masses onto the cooling spot in clusters of galaxies.21–24 In a related vein for the fusion plasma, it is well known that the convective scaling of electron thermal conduction is obtained at the entrance of the steady-state sheath, in which the plasma is nearly collisionless, as a result of the ambipolar transport.25–27 In this paper, we will show that the convective scaling with the parallel ion flow, in the electron thermal conduction itself or its spatial gradient, can be established throughout the bulk, quasineutral, and nearly collisionless plasma away from the wall due to ambipolar constraint. Such convective scaling comes about because the cooling of the surrounding plasma takes the form of propagating fronts that originate from the cooling spot and the fundamental ambipolar transport constraint between the slow fronts modifies the thermal conduction heat flux. As a result, a robust plasma cooling flow into the cooling spot will be developed due to the retained large electron temperature and hence pressure gradient.28 Such weaker convective scaling of the electron thermal conduction, via itself or its gradient, is also critically important for a slower TQ of the fusion plasmas by modifying the core plasma cooling processes.29 This should be contrasted with a straightforward application of the flux-limiting form for electron parallel thermal conduction, which would yield a much faster TQ on a timescale that is around a factor of m i / m e faster. Had one unwisely deployed the Braginskii parallel thermal conductivity instead for such a nearly collisionless plasma, an even faster TQ would be obtained in numerical simulations if the plasma has collisional mean-free path longer than the system size.

Here, we follow the previous letter of Ref. 28 on the subject and present the details of numerical diagnostics, the analyses of the propagating fronts' characteristics, and the underlying physics, as well as the electron thermal conduction flux. First-principles fully kinetic simulations were performed with the VPIC30 code to investigate the parallel transport physics in the TQ of a nearly collisionless plasma. A prototype one-dimensional slab model is considered with a normalized background magnetic field, where an initially uniform plasma with constant temperature T 0 10 keV and density n 0 10 19 m 3 is filled the whole domain. The plasma is signified as semi-infinite with the right simulation boundary simply reflecting the particles. We notice that such a boundary condition would not affect the plasma dynamics as long as the later-defined electron fronts have not arrived there yet. This indicates that we consider t < L B / v t h , e. However, for longer timescale, the basic physics holds, which affects the TQ processes.29 A cooling spot is modeled at the left boundary as a thermobath that mimics a radiative cooling spot, which conserves particles by re-injecting electron–ion pairs (equal to the ions across the boundary) with a radiatively clamped temperature T w T 0. For comparison, an absorbing boundary, as a sink to both the particles and energy that absorbs all the particles hitting the left boundary, is also considered for simulations. We found that these two types of cooling spots show remarkable similarities in plasma cooling so the absorbing boundary is quite useful for understanding the underlying physics.

For both thermobath and absorbing boundaries, the TQ is found to be governed by the formations of propagating fronts (see Fig. 1). Particularly, for the former (latter), there are four (three) fronts: the first two have speeds scale with the electron thermal speed v t h , e and, thus, are named electron fronts, while the other two (one) propagate at speeds that scale with the local ion sound speed cs and thus named ion fronts. Based on the underlying physics and their roles in the TQ dynamics, these fronts can be named the precooling front (PF), precooling trailing front (PTF), recession front (RF), and cooling front (CF, for the thermobath boundary only), respectively, as illustrated in Fig. 1. The precooling and recession fronts describe the onset of T cooling of electrons and ions, respectively, which are independent of the cooling spot types. In contrast, the precooling trailing and cooling fronts will not only play a role in T cooling but also reflect the onset of T cooling via the dilution with the cold recycled particles for the thermobath boundary. It should be noted that the propagating fronts for the rapid cooling of a nearly collisionless plasma, as described and reported here, are not the artifact of the boundary conditions deployed in the simulation. In a forthcoming paper that focuses on the impurity ion assimilation by a cooling plasma, the same front propagation physics are found in a plasma where a hot and dilute plasma cools against a cold and dense plasma that is initially in pressure balance between the two regions.

FIG. 1.

Normalized electron and ion temperature (by T0) and electrostatic potential (by T 0 / e) at ω p e t = 163 for the thermobath boundary with T w = 0.01 T 0 (a) and the absorbing boundary (b) from the first-principles kinetic simulations of collisionless plasma (similar results are obtained for nearly collisionless plasma with λ mfp L B). Notice that the perpendicular temperature for the absorbing boundary is nearly unperturbed and hence ignored. The sheath entrance here is denoted as where the plasma parameters remain quasi-steady. We should emphasize that the electrostatic potential is directly integrated from the instantaneous electric field that contains large amplitude Langmuir waves, which thus is only used as a guide for the qualitative behavior of the quiescent ambipolar potential.

FIG. 1.

Normalized electron and ion temperature (by T0) and electrostatic potential (by T 0 / e) at ω p e t = 163 for the thermobath boundary with T w = 0.01 T 0 (a) and the absorbing boundary (b) from the first-principles kinetic simulations of collisionless plasma (similar results are obtained for nearly collisionless plasma with λ mfp L B). Notice that the perpendicular temperature for the absorbing boundary is nearly unperturbed and hence ignored. The sheath entrance here is denoted as where the plasma parameters remain quasi-steady. We should emphasize that the electrostatic potential is directly integrated from the instantaneous electric field that contains large amplitude Langmuir waves, which thus is only used as a guide for the qualitative behavior of the quiescent ambipolar potential.

Close modal

The rest of the paper is organized as follows: In Sec. II, we elucidate the underlying physics of electron fronts, while the ion front(s) physics are investigated in Sec. III. The electron thermal conduction flux within the recession layer (the region between the recession and cooling front for the thermobath boundary or between the recession front and sheath entrance for the absorbing boundary), which is essential for the formation of the plasma cooling flow, will be discussed in Sec. IV. We will conclude in Sec. V.

We first investigate the physics underlying the electron fronts. In a nearly collisionless plasma, the cooling of the parallel electron temperature T e is mainly due to the cutoff of electron distribution function as a result of the loss of high energy electrons that overcome the electrostatic potential barrier, i.e., v > v c where v c = 2 e Δ Φ / m e with Δ Φ = Φ ( x ) Φ min , Φ ( x ) being the local electrostatic potential and Φ min the minimum potential. For the absorbing boundary, Φ min is the boundary potential, while for the thermobath boundary, Φ min is the local minimum potential just behind the cooling front as shown in Fig. 1. It must be highlighted that for the thermobath boundary, the same ambipolar field can accelerate some cold recycled electrons toward the upstream to form an electron beam with velocity V b v c due to the energy gain at the ambipolar potential (see Fig. 2), the front of which is between the electron fronts that will be discussed later in this section. As a result, the electron distribution can be approximated as
(2)
where Θ ( x ) is the Heaviside step function that vanishes for x < 0, δ ( x ) is the Dirac delta function, nm is the plasma density associated with the cutoff Maxwellian (the original surrounding electrons), and nb is the recycled (cold) electron beam density. For the absorbing boundary (or ahead of the cold electron beam front for the thermobath boundary), nb = 0, for which one obtains
(3)
(4)
(5)
(6)
FIG. 2.

Electron distributions at different locations from VPIC simulations corresponding to Fig. 1. (a) Thermobath boundary and (b) absorbing boundary. These distributions are chosen from: (1) ahead of the precooling front, (2) between the precooling and precooling trailing fronts (for the thermobath boundary, it is ahead of the cold electron beam front where T e is unperturbed), (3) between the recession and precooling trailing fronts, and (4) within the recession layer. For the thermobath boundary, ( 2 ) is behind the cold electron beam front but ahead of the precooling trailing front.

FIG. 2.

Electron distributions at different locations from VPIC simulations corresponding to Fig. 1. (a) Thermobath boundary and (b) absorbing boundary. These distributions are chosen from: (1) ahead of the precooling front, (2) between the precooling and precooling trailing fronts (for the thermobath boundary, it is ahead of the cold electron beam front where T e is unperturbed), (3) between the recession and precooling trailing fronts, and (4) within the recession layer. For the thermobath boundary, ( 2 ) is behind the cold electron beam front but ahead of the precooling trailing front.

Close modal

Here, n e = f e d 3 v is the electron density, V e = v f e d 3 v / n e is the parallel electron flow, T e = m e v ̃ 2 f e d 3 v / n e is the parallel electron temperature, and q e n = m e v ̃ 3 f e d 3 v is the parallel thermal conduction flux of the parallel degree of freedom,31 where v ̃ ( v V e ).

The ambipolar transport constraint implies V e V i , one immediate result of which is that the last terms in T e and qen that are proportional to V e 2 , 3 are negligible as V e V i < ̃ v t h , i v c v t h , e with v t h , i = T 0 / m i. This is especially so between the electron fronts where the plasma flow is nearly unperturbed since it is controlled by the ion fronts. Without the plasma flow ahead of the ion fronts, the plasma energy equation shows that the collapse of T e is mainly driven by the conduction heat flux qen,
(7)
Between the electron fronts, the fraction of electron beam for the thermobath boundary is small n b n m (notice that nb = 0 for the absorbing boundary). Thus, the ambipolar transport constraint V e V i requires v c > 2 v t h , e as seen from Eq. (4) and Fig. 2. Such a condition guarantees that
(8)
As a result, the energy equation in Eq. (7) has the solution T e = T e ( x v c t ) for n e n 0, revealing that vc is the recession speed of T e or the velocity space void in f e ( v ) propagates upstream with a speed of vc. It must be emphasized that the electron fronts are fast v t h , e but only produce a modest amount of T e cooling as seen from Eq. (5) for v c v t h , e, which results from the ambipolar transport constraint. Moreover, Eq. (6) illustrates that the electron parallel conduction flux does scale as the free-streaming limit, q e n n e v t h , e T 0 but with a small coefficient as a function of v c ( Φ ).
Now we can define the electron fronts and provide their propagating speeds by using the local vc. The precooling front (PF) is used to denote the onset of T e cooling, which can be defined as where T e ( v c ) has a detectable cooling. It is independent of the boundary condition since it is ahead of the recycled electron beam front. Considering the VPIC noise, we choose the speed of the PF as
(9)
for which T e ( v c = U P F ) 0.95 T 0 as seen from Eq. (5) with nb = 0. It agrees well with the simulation results in Fig. 3. While the precooling trailing front (PTF) comes about because the ambipolar potential and hence the plasma cooling mainly varies behind the recession front (see Fig. 1) due to the limit of the plasma flow. Therefore, there must be a smallest cutoff velocity v c min = 2 e ( Δ Φ ) RF / m e v t h , e ahead of the recession front (RF) determined by the reflecting potential, ( Δ Φ ) RF = Φ RF Φ min with Φ RF being the potential at the RF. Such v c min will define the PTF speed as
(10)
FIG. 3.

Contour plots of normalized electron temperature and the corresponding fitting precooling front (black triangles) for the same simulations in Fig. 1, where the left boundary conditions are labeled. For the thermobath boundary, we also plot the fitting front of T e collapse (black diamonds). The nearly unperturbed values are colored as magenta.

FIG. 3.

Contour plots of normalized electron temperature and the corresponding fitting precooling front (black triangles) for the same simulations in Fig. 1, where the left boundary conditions are labeled. For the thermobath boundary, we also plot the fitting front of T e collapse (black diamonds). The nearly unperturbed values are colored as magenta.

Close modal
The fact that the cutoff velocity between the PTF and RF satisfies v c v c min demonstrates that the PTF will leave a nearly constant T e = T e ( U PTF ) behind. For an absorbing boundary with nb = 0, from Eq. (5) we obtain
(11)
For the thermobath boundary, the aforementioned cold electron beam, which is accelerated by the electrostatic potential all the way to U PTF, will reduce T e ( U PTF ). This is because such an electron beam will reduce the reflecting potential for the thermobath boundary compared to that for the absorbing boundary as shown in Fig. 1 (this will be studied in Sec. IV), which results in a slower PTF (smaller UPTF) and, hence, deeper cooling of T e than those for the absorbing boundary.

Interestingly, the faster PTF for the absorbing boundary nearly coincides with the T e collapse front (cold recycled electron beam front) for the thermobath boundary as shown in Fig. 1. This is because, at the beginning of the thermal collapse, the number of recycled electrons is not high enough to cause an appreciable reduction of the reflecting potential compared to that for the absorbing boundary. Such nearly equalized reflecting potential ( Δ Φ ) RF will accelerate the recycled electrons, which dilutely cool T e , to UPTF for the absorbing boundary case. A fitting speed of 1.4 v t h , e for T e precooling front is shown in Fig. 3.

The ion front(s) not only describes the plasma temperature cooling, but also controls the plasma density evolution and the associated cooling flow generation. This section is dedicated to study the underlying physics of the ion front(s), taking into account that the plasma thermal conduction is forced to be convective, in the form of either itself or its gradient, due to the ambipolar transport, which will be investigated in Sec. IV. As a result, the electron pressure gradient remains large to drive plasma flow toward the cooling spot, which is known in astrophysics as the cooling flow.21–24 

We first highlight that the cooling front (CF) for the thermobath boundary case is the front of cold recycled ions. Therefore, the plasma ahead the CF is free of cold recycled ions. Such a block of cold ions by the CF is complete and, thus, different from that of the cold recycled electrons discussed above, where some of them can cross the CF and penetrate into the upstream plasma as cold recycled electron beams. As a result, we can examine the recession front (RF) and the recession layer between the RF and CF by ignoring the recycled ions. In physics terms, the recession layer is a rarefaction wave in the nearly collisionless plasma, which is different from the rarefaction wave formed in a cold plasma interacting with a solid surface32–34 considering the large plasma temperature and pressure gradients and the nature of the plasma heat fluxes. However, the common feature of the rarefaction wave is that the plasma parameters recede steadily with local speed c s and thus we can seek self-similar solutions of n e , i , V e , i , T e , i as functions of the self-similar variable ξ x / t c s from the minimum model for an anisotropic plasma,31,35,36
(12)
(13)
(14)
The force balance of electrons e n e E p e / x and the quasi-neutral condition ne = Zni are used with Z being the ion charge number, and p e , i = n e , i T e , i . Notice that the quasi-neutrality ensures V e V i v t h , e in the absence of net current and thus the force balance of electrons is valid within the recession layer due to the small inertia of electrons.
To complete these equations, we need closures for the parallel ion thermal conduction of the parallel degree of freedom q i n m i ( v V i ) 3 f i d v and the electron pressure gradient. Within the recession layer, the ion distribution can be approximated by one-sided cutoff Maxwellian with a proper shift like in the presheath region,27 and thus, we can employ q i n = σ i T i Γ i with σ i 1 the energy transmission coefficient and Γ i = n i V i . The spatial gradient of qen is shown to retain the convective energy transport scaling n e V e T e over the recession layer (see Sec. IV) so that we can approximate q e n / x σ e ( n e T e V i ) / x, where σ e 1 is analogous to σi. As a result, from the continuity and energy equations for ions in Eqs. (12) and (14) and electrons, which have the same form as Eqs. (12) and (14) but with e replacing i in the subscripts, we obtain
(15)
Recalling the quasi-neutral condition V e V i , one finds
(16)
where μ = ( 3 + σ e ) / ( 3 + σ i ) × [ ξ + ( 1 + σ i ) V i ] / [ ξ + ( 1 + σ e ) V i ] 1. In physics terms, Eq. (16) demonstrates a universal length scale for p e , i within the recession layer since the convective transport scaling dominates the thermal collapse of T e , i . As a result, Eqs. (12)–(14) form a complete set of equations in the form of
(17)
where A is a matrix of ni, V i , and T e , i . The non-trivial solution requires det ( A ) = 0, yielding
(18)
where c s = 3 ( μ Z T e + T i ) / m i is approximated to the local ion sound speed. A uniquely monotonic solution of ξ can be found in the recession layer as
(19)
by ignoring the explicit dependence on ξ of μ in cs. It shows that the recession speed ξ is determined by the local ion flow and sound speed, and thus, the recession layer is independent of the boundary condition (see Fig. 4). This is not surprising since the cold ions are blocked by the CF, while the recycled electron beam only moderately modifies the electron profiles ahead of the CF.
FIG. 4.

Profile of normalized ion density, parallel flow and temperature at ω p e t = 1357 for the simulations in Fig. 1. The location of the cooling front is marked, ahead of which the ion state variables are aligned with each other for different boundary conditions.

FIG. 4.

Profile of normalized ion density, parallel flow and temperature at ω p e t = 1357 for the simulations in Fig. 1. The location of the cooling front is marked, ahead of which the ion state variables are aligned with each other for different boundary conditions.

Close modal
Let us first use the self-similar solution of Eq. (19) to recover a known constraint on the plasma exit flow at an absorbing boundary where a non-neutral sheath would form next to it. The sheath entrance cannot propagate further upstream in this case so ξ = 0. Thus, Eq. (19) predicts an ion exit flow speed of
(20)
with
(21)
and Γ e , i = n e , i V e , i . This is consistent with the Bohm criterion for plasma in steady state ( d / d t = 0) when including the heat flux in the transport model.37–39 More importantly, Eq. (19) predicts the speed of the RF, which is defined as V i = 0,
(22)
Recalling Eqs. (12)–(14), such definitions of the RF also denote the onset of ni and T i drop. Moreover, since the electron temperature is only moderately reduced at the RF, T e T e ( U PTF ), we have U R F 2.8 v t h , i for Z = 1 and μ = 1 from Eq. (22). This is consistent with the VPIC simulations as shown in Fig. 5.
FIG. 5.

Contour plots of the normalized ion temperature and the corresponding fitting recession front (black squares) for the same simulations in Fig. 1, where the left boundary conditions are labeled. For the thermobath boundary case, we also plot the fitting cooling front (black stars), which denotes the onset of T i collapse. The nearly unperturbed values are colored as magenta.

FIG. 5.

Contour plots of the normalized ion temperature and the corresponding fitting recession front (black squares) for the same simulations in Fig. 1, where the left boundary conditions are labeled. For the thermobath boundary case, we also plot the fitting cooling front (black stars), which denotes the onset of T i collapse. The nearly unperturbed values are colored as magenta.

Close modal

The cooling front (CF) in the thermobath boundary case is where the hot ions meet the cold ions as illustrated in Fig. 6. In fact, it is a shock front, across which all the plasma state variables have jumps as shown in Figs. 1–5. Particularly, the ions undergo heating in the parallel direction when the plasma flow runs into the CF, where the substantial ion flow energy in the recession layer is converted into ion thermal energy as shown in Figs. 1, 4, and 5. Such conversion is via the mixing of the cooling flow ions with the cold recycled ions (see Fig. 6), the latter of which are accelerated from the boundary to the CF by the inverse pressure gradient due to the pressure pileup at the boundary. As a result, these cold recycled ions will offset the plasma flow generated by the surrounding ions as shown in Fig. 4. In sharp contrast to ions, the electrons will undergo cooling via dilution with high-density cold electrons so that T e T w behind the CF as shown in Figs. 1 and 3. Moreover, the presence of the CF and the associated cooling zone behind the CF is of fundamental importance to T i and T e cooling via dilution and thus the CF represents a deep cooling of electrons.

FIG. 6.

Ion distribution just ahead (a) and behind (b) the cooling front for the thermobath boundary case corresponding to Fig. 1. Here, v is the velocity in the parallel direction, while v is the velocity in one of the perpendicular directions. Behind the cooling front, there are two components in the ion distribution, which have quite different perpendicular temperature, indicative of the cooling flow ions from the upstream and cold recycled ions from the boundary.

FIG. 6.

Ion distribution just ahead (a) and behind (b) the cooling front for the thermobath boundary case corresponding to Fig. 1. Here, v is the velocity in the parallel direction, while v is the velocity in one of the perpendicular directions. Behind the cooling front, there are two components in the ion distribution, which have quite different perpendicular temperature, indicative of the cooling flow ions from the upstream and cold recycled ions from the boundary.

Close modal
To find the speed of the shock (cooling) front, we can match the conserved quantities across the front while simply ignoring the thermal conduction flux due to the convective scaling of its gradient. In the moving frame of reference with the shock front, we have
(23)
(24)
(25)
where subscripts 1 and 2 denote, respectively, the ion variables behind (downstream) and ahead (upstream) of the shock front, and V ̃ i = V i U C F with UCF being the CF speed. As a result, we find
(26)
In the upstream (recession layer), we have shown that V i + ξ = c s = 3 ( Z T e + T i ) / m i as seen from Eq. (19) with σ i = 0. Therefore, the Mach number M 2 = | V i U C F | / c s is near unity and thus the CF is a low Mach number shock. It should be noted that, near the CF, the ion flow is further accelerated by the large ambipolar field compared to that for the absorbing boundary (see Fig. 4), increasing M2 slightly above the unity. These conditions ensure the stable flow upstream and downstream of the shock.40 Further simplification to obtain the CF speed will be | V i 1 | U C F due to the offset of plasma velocity by the cold recycled particles as shown in Fig. 4 so that
(27)
with M 2 1. This indicates that the CF propagates with the upstream ion sound speed. Since the plasma temperature at the CF is considerably lower than that at the RF, we have U C F < U R F .

In this section, we investigate the electron thermal conduction flux within the recession layer under the ambipolar transport constraint V e V i . Both model analyses and first-principles simulations using VPIC will be provided.

For the electron distribution in Eq. (2), the electron density, parallel flow, temperature, and thermal conduction heat flux are given in Eqs. (3)–(6), respectively, from which one finds an expression for T e and qen as follows:
(28)
(29)
Then from Eqs. (4), (28), and (29), we see that the impact of the cold beam can be ignored in the limit of a small cold beam component
(30)
Since v c v t h , e , one has in this limit
(31)
under which we cover the absorbing boundary case with nb = 0. Otherwise, the cold beam can make a big difference.
For an absorbing boundary or a small beam component, the ambipolar transport will limit the cutoff velocity to be large v c v t h , e 2 ln ( v t h , e / V i ) , so that V e V i as seen from Eq. (4). However, in the large cold beam component limit,
(32)
or equivalently, n b / n e m e / m i, one must have, to the leading order in m e / m i ,
(33)
which means that the cold beam and the truncated Maxwellian both carry significant electron particle fluxes, but nearly cancel each other to produce a much slower electron flow V e that matches onto V i for ambipolar transport. Compared to the small beam component limit, the requirement for large vc and, hence, Δ Φ in the absorbing boundary case is relaxed due to the large electron beam component. Therefore, the reflecting potential and, hence, UPTF for the thermobath boundary is smaller than those for the absorbing boundary as discussed in Sec. II. From Eqs. (3) and (33), we obtain
(34)
One can easily verify that n b / n e is a monotonically decreasing function of vc. It is important to note that vc cannot vanish (or nb = ne), otherwise, T e would become negative as seen from Eq. (28). However, vc can become very small and so does T e , indicating that the plasma temperature can drop to the value set by the temperature of the beam-like cold plasma at the CF.
The necessary constraint to sustain the large gradient of T e within the recession layer to drive the plasma flow toward the cooling spot is on the spatial gradient of qen, which can be argued in the following. Assuming the recession layer span a length of LR, from Eq. (7), the convective energy transport terms (the term that is proportional to V e itself or its gradient) follow the scaling of n e T e V e / L R. Therefore, a necessary condition for forming the recession layer by keeping a large T e gradient will require
(35)
This is indeed the case due to the ambipolar transport constraint. To see it, we re-write qen in Eq. (29) as
(36)
where
(37)
(38)
The second term carries over from the absorbing boundary case where no cold electron beam component is present, while the first term is entirely due to the presence of a cold beam component, as it is proportional to n b / n e. This first term is of great importance since it covers the conventional electron free-streaming scaling of qen, although the coefficient critically depends on the fractional density of the cold beam component.
In the case of an absorbing boundary, n b / n e = 0 , we have
(39)
which illustrates that the parallel electron heat flux itself scales as the convective energy transport scaling. While in the large cold beam limit, the first term of qen dominates
(40)
for v c > V e so that qen itself has electron mass scaling m e 1 / 2, recovering the free-streaming limit. However, its spatial gradient over the recession layer retains the convective transport scaling. This is because the cold beam continuity equation in the collisionless recession layer has
(41)
to obtain which we have ignored n b / t in the beam continuity equation because if we seek the self-similar solution between the ion fronts, we have n b / t ξ n b / x v c n b / x with ξ c s v c v t h , e. This indicates that ( n b v c ) / x = n b / t c s n b / L R contributes less to q e n / x than that from the second term in Eq. (36) since nb < ne. Therefore, we have reached the interesting point that the electron parallel heat flux is primarily carried by the electron beam to follow the free electron streaming scaling, but remarkably, its spatial gradient is given by the convective energy transport scaling.

The first-principles kinetic simulations have confirmed all the above analytical results. Specifically, to check the convective transport scaling of qen, i.e., q e n m i 1 / 2, we have conducted simulations by employing different ion-electron mass ratios, i.e., m i / m e = 100 , 400 , 900, and 1600. Equation (19) indicates that both the ion flow and local recession speed ξ in the recession layer scales with m i 1 / 2. Therefore, to overlap the recession layer to the same location for different mi, we should choose temporal moments with constant ω p i t for different cases. Here, ωpi is the ion plasma frequency.

In Fig. 7, we plot the profiles of qen for the absorbing boundary case, which demonstrates that qen itself indeed follows the convective transport scaling q e n V i within the recession layer, although the coefficient σe slightly increases with mi. Such a variation of σe comes from the weakly positive dependence of vc on mi via v c v t h , e 2 ln ( v t h , e / V i ).

FIG. 7.

Profiles of qen at ω p i t = 20.3 for different m i / m e with the absorbing boundary. Left: qen, normalized by the initial quantities n 0 T 0 v t h , e, at the whole domain, where the recession front at x 60 λ D is labeled by the vertical dashed line; Right: qen, normalized by the convection heat flux 3 n e V i T e , behind the recession front (away from the recession front where V i 0).

FIG. 7.

Profiles of qen at ω p i t = 20.3 for different m i / m e with the absorbing boundary. Left: qen, normalized by the initial quantities n 0 T 0 v t h , e, at the whole domain, where the recession front at x 60 λ D is labeled by the vertical dashed line; Right: qen, normalized by the convection heat flux 3 n e V i T e , behind the recession front (away from the recession front where V i 0).

Close modal

For the case of a thermobath boundary, Fig. 8 shows that qen is nearly independent of mi and instead recovers a flux-limiting form for the heat conduction flux with α e 0.2 in the recession layer. However, its gradient within the recession layer still has the convective transport scaling, i.e., d q e n / d x m i 1 / 2. As discussed in Eq. (36), the free-streaming form is recovered for qen because of the dominating cold beam contribution of 2 n b v c T 0. This cold beam term, however, does not contribute to d q e n / d x since the cold beam flux n b v c in the collisionless recession layer is constant as shown in Eq. (41). To quantify the beam contribution to the electron heat flux as well as the particle flux, we have separated the cold recycled electrons from the original electrons. In Fig. 9, we show the contributions to the electron particle flux n e V e from both recycled n b v c and the original trapped electrons n m V m n e V e n b v c for the m i = 100 m e case. It shows that both the recycled and the original trapped electrons carry significant electron particle flux but nearly cancel each other to generate much smaller n e V e n b v c. Notice that n b v c has the electron scaling n b v c v t h , e while n e V e has the ion scaling n e V e v t h , i so that the difference between them is even stronger for larger mi. Figure 9 also confirms that n b v c is nearly constant within the recession layer as expected, so it does not contribute to d q e n / d x. It is worth noting that the cold electron front is ahead of the PTF. Ahead of the PTF, n b v c varies in space so that qen itself and its gradient continuously follow the free-streaming scaling.

FIG. 8.

Profiles of qen (left) and its averaged gradient d q e n / d x (right) in the recession layer at ω p i t = 13.6 for the thermobath boundary with T w = 0.01. The averaged region in the recession layer is labeled by vertical dashed lines.

FIG. 8.

Profiles of qen (left) and its averaged gradient d q e n / d x (right) in the recession layer at ω p i t = 13.6 for the thermobath boundary with T w = 0.01. The averaged region in the recession layer is labeled by vertical dashed lines.

Close modal
FIG. 9.

n e V e , n b v c, and n m V m n e V e n b v c, in the unit of n 0 v t h , e, at ω p e t = 271 for the thermobath boundary with m i / m e = 100 and T w = 0.01. The locations for the four fronts are labeled.

FIG. 9.

n e V e , n b v c, and n m V m n e V e n b v c, in the unit of n 0 v t h , e, at ω p e t = 271 for the thermobath boundary with m i / m e = 100 and T w = 0.01. The locations for the four fronts are labeled.

Close modal

In conclusion, the thermal collapse of a nearly collisionless plasma interacting with a cooling spot is both theoretically and numerically investigated. For both types of cooling spots that signify, respectively, the radiative cooling masses (thermobath boundary) and a perfect particle and energy sink (absorbing boundary), we found that the thermal quench comes about in the form of propagating fronts that originate from the cooling spot. Particularly, for the thermobath boundary, two fast electron fronts have speeds that scale with the electron thermal speed v t h , e, and two slow ion fronts propagates at local ion sound speed cs. The former denotes the fast but moderate cooling of electrons, while the latter represents the slow but aggressive cooling of electrons and ions.

The underlying physics behind these propagating fronts have been investigated, in which the electron thermal conduction heat flux qen is found to play an essential role. Specifically, the electron fronts are completely driven by q e n , which follows the free-streaming form ( q e n n e v t h , e T e ). Such large thermal conduction flux is reminiscent of a very limited amount of T e drop over a very large volume. In contrast, the ion fronts are formed as a result of the full transport physics, the crucial one of which is the ambipolar transport constraint. Due to such ambipolar transport constraint, qen in the recession layer itself follows the convective energy transport scaling with the parallel plasma flow V i for the absorbing boundary. While for the thermobath boundary, the cold electron beam will restore the free-streaming limit of q e n 2 n b v c T 0 v t h , e, but its spatial gradient will follow the convective transport scaling since the beam particle flux ( n b v c) remains nearly constant within the recession layer. As a result, the electron temperature and, hence, the pressure retain large spatial gradient to drive the plasma flow toward the cooling spot.

For a thermobath boundary that provides an energy sink while re-supplying cold particles, the plasma cooling flow eventually terminates against the cooling spot via a plasma shock, which we named the cooling front since it signifies the deep cooling of electrons to the radiatively clamped temperature Tw. It is shown that such a shock front will convert the ion flow energy into the ion thermal energy via the mixing of hot and cold ions behind the front, which completely blocks the cold ions from migrating upstream. Therefore, the cooling front and the associated cooling zone behind the cooling front are of fundamental importance to T i and T e cooling via dilution. Unlike the recycled cold ions, part of the recycled electrons can penetrate through the cooling front to reach the electron fronts, causing further cooling of the electrons behind the electron fronts.

We thank the U.S. Department of Energy Office of Fusion Energy Sciences and Office of Advanced Scientific Computing Research for support under the Tokamak Disruption Simulation (TDS) Scientific Discovery through Advanced Computing (SciDAC) Project and the Base Theory Program, both at Los Alamos National Laboratory (LANL) (Contract No. 89233218CNA000001). This research used resources of the National Energy Research Scientific Computing Center (NERSC), a U.S. Department of Energy Office of Science User Facility operated (Contract No. DE-AC02–05CH11231) and the LANL Institutional Computing Program, which is supported by the U.S. Department of Energy National Nuclear Security Administration (Contract No. 89233218CNA000001).

The authors have no conflicts to disclose.

Yanzeng Zhang: Data curation (equal); Formal analysis (equal); Investigation (equal); Methodology (equal); Software (equal); Validation (equal); Visualization (equal); Writing – original draft (lead); Writing – review & editing (equal). Jun Li: Conceptualization (equal); Investigation (equal); Methodology (equal); Software (equal); Validation (equal); Writing – original draft (supporting); Writing – review & editing (equal). Xian-Zhu (X. Z.) Tang: Conceptualization (equal); Formal analysis (equal); Funding acquisition (lead); Investigation (equal); Methodology (equal); Project administration (lead); Resources (equal); Supervision (lead); Validation (equal); Writing – original draft (supporting); Writing – review & editing (equal).

The data that support the findings of this study are available within the article.

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