A Powerful Remote Source of O Atoms for the Removal of Hydrogenated Carbon Deposits
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- Zaplotnik, R., Vesel, A. & Mozetic, M. J Fusion Energ (2013) 32: 78. doi:10.1007/s10894-012-9530-8
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We describe a system to deliver a large flux of O atoms for the removal of hydrogenated carbon films from surfaces in remote areas of tokamaks with carbon divertors. The oxygen plasma is generated via electrode-less radiofrequency discharge in a discharge chamber connected to a remote chamber by a 2 m long complex-shaped glass tube 4 cm in diameter. The density of O atoms in the remote chamber was measured with a nickel catalytic probe and its variation with discharge power obtained. The density was close to the detection limit of the probe (around 1 × 1019 m−3) as long as the vacuum system was pumped with a rotary pump at a nominal pumping speed of 80 m3 h−1. The density increased well over 1020 m−3 when a Roots pump was added. The effective pumping speed at the current setup was up to 200 m3 h−1. At such conditions, the maximal O-atom density at 2 m from the source was up to 3 × 1020 m−3. The density depended on the pressure as well as the discharge power. The behavior of O-atom density far away from the source was explained by gas phase and surface phenomena. The effective pumping speed was found to be of crucial importance. The setup was used for removal of model hydrogenated carbon films. Experiments were performed at sample temperatures up to 600 K and etching rates up to 50 nm/s were obtained. We found that the experimental setup is suitable for removal of hydrogenated atoms on a large scale.
KeywordsOxygen plasma Source of neutral oxygen atoms O-atom density Hydrogenated carbon removal Cleaning tokamak divertors
As a promising energy source for future generations, nuclear fusion of heavy hydrogen isotopes still attracts interest. Fusion is obtained by different means but the most promising is from magnetically-confined high-temperature hydrogen plasmas. Magnetic confinement enables high plasma temperatures to be sustained as well as reasonable discharge duration. Several confinement configurations have been applied including large tokamaks. In such devices, plasma-facing components are subject to extreme conditions from hot gaseous particles interacting with solid material. The most severe conditions are found in the divertors where the power density is of order 10 MW m−2. The divertor materials must withstand such conditions to ensure proper operations. Various materials have been tried in the construction of the first wall blankets; currently carbon and tungsten seem to be the most suitable. Both materials have, however, disadvantages; tungsten, a high-Z material, causes substantial plasma cooling in the discharge volume even in small concentrations, whereas carbon suffers from chemical sputtering. The resultant CHx radicals stick to the surfaces in remote parts of a tokamak causing the formation of hydrogenated carbon deposits. Not only does chemical sputtering cause erosion of the first wall material, and thus modification of the divertor components dimensions, but also retains radioactive tritium, thereby creating a bigger problem . Although, thermo-mechanical properties of carbon fiber composites (CFCs) are superior in comparison to tungsten, the interaction of high-energy neutrons with carbon materials causes radiation damage, localized amorphization, and thus a loss of otherwise excellent thermomechanical properties. Nowadays, it is believed that, although CFCs have remained the material to form the blankets of the most exposed parts of divertors in the initial operation stage of the international experimental fusion reactor ITER, these will not be used in commercial fusion devices.
Since chemical erosion of carbon cannot be avoided, many researchers worldwide are currently occupied with the development of techniques to suppress carbon hydrogenation. A promising technique to minimize H-C deposition is puffing nitrogen-containing gases into recesses in the divertor. Recent experiments showed that the technique allows for the important reduction of H-C depositions through the molecular formation of HCN, which by not sticking to the walls are easily pumped out [2, 3, 4]. Scavenger techniques, however, do not prevent deposition completely so researchers have developed techniques for the occasional removal of these deposits. Carbon deposits can be removed with different techniques, e.g. with pulsed-laser  or with oxidation, which can be divided into three categories: plasma driven, activated oxygen and thermo-oxidation [6, 7, 8]. Applications of mild plasma of oxygen, hydrogen, or nitrogen (ammonia) were found suitable [9, 10, 11, 12, 13, 14, 15] but this technique cannot be applied in ITER because of the strong permanent magnetic fields produced by superconducting magnets. Nonetheless, the erosion rates for hydrogenated carbon deposits were found suitable ~2.1 × 1019 C/s . Also, it was found that the probability for the removal of a carbon by a positively-charged oxygen ion is well over 100 %. That paradox has been explained as the removal of C atoms from hydrogenated carbon films by other reactive particles found in the oxygen plasma. The primary candidates are neutral oxygen atoms.
Neutral oxygen atoms can be produced in different oxygen plasma discharges. Average neutral oxygen atom densities measured in these discharges are: ~1×1021 m−3 in a DC discharge , ~5×1020 m−3 in a microwave discharge , ~1×1020 m−3 in a capacitively coupled RF plasma (CCP) , ~2×1021 m−3 in an oxygen plasma created by electrode-less high-frequency discharges (ICP) [19, 20, 21, 22, 23, 24, 25]. In inductively coupled plasmas, because of relatively-low dissociation energies for oxygen molecules as compared with their ionization energy, and due to a relatively low probability for recombination on chamber walls, the dissociation fraction in plasma created in such discharges easily exceed 10 %. This is orders of magnitude larger than the ionization fraction in mild plasmas. The huge difference between the dissociation and ionization fractions has been attributed to the minimal loss of O atoms on surfaces; the recombination coefficient depends on the type of material facing the plasma and can be as low as 10−5 for some glasses [26, 27, 28, 29]. The probability for surface neutralization of charged particles, in contrast, is close to 1.
High chemical reactivity of neutral oxygen atoms and ease of production have led to various experiments on the removal of hydrogenated carbon deposits by interaction with atoms but only with the absence of all other plasma particles. First results showed that the reaction probability could be appreciatively high at elevated temperatures. Removal rates exceeding 10 nm s−1 have been reported [30, 31]. The cited results have been obtained in small experimental systems with typical sample size of the order of cm2. The problem with this technique, as with most others, however, is in scaling up the experimental conditions so that the method can be used in the removal of deposits in large fusion reactors. Total surface areas of the order of 100 m2 are typical.
Removal of hydrogenated carbon deposits with neutral oxygen atoms over large areas requires the development of a huge source of O atoms as well as techniques for transferring atoms from discharge to those recess areas. As mentioned earlier, the source cannot be placed inside the main tokamak vessel; the closest suitable place is about 2 m away from the large tokamak divertor. In transfer, atoms can be lost because of recombination hence the O-atom density in the interior of the divertor will be much lower than in the discharge area itself. To show the viability of this technique in removing deposits from recesses, we developed a large O atom source and delivery system comprising a reaction chamber attached with a rather complex-shaped tube 2 m in length. The complex shape is to simulate possible access routes to the recesses in the divertor. Details and tests of the setup are presented in this paper.
Catalytic Probe Results
It is worth mentioning that attempts were made to measure the O-atom density in the remote chamber while using only the rotary pump for pumping, but the measured signal was always close to the detection limit of our probe which presently is close to 1 × 1019 m−3. The occurrence of such a low density under these pumping conditions will be explained in detail below.
As mentioned above, the density of O atoms in the remote chamber was, while using only the rotary pump, immeasurable in practical terms. A crucial parameter is obviously the effective pumping speed. The influence of pumping speed is best observed in Fig. 12. The ratio between the O-atom density at the edge of the discharge chamber and in the remote chamber decreases monotonically with increasing effective pumping speed. At low pumping speeds the ratio is higher than 100. Considering the results plotted in Fig. 12, the nominal pumping speed of the rotary pump is 80 m3 h−1, but if using just this pump the effective pumping speed is only as high as 30 m3 h−1 (see Fig. 5). Extrapolating the curve presented in Fig. 12 to the effective pumping speed 30 m3 h−1 would give a huge difference between the O-atom density in the discharge and in the remote chamber.
An important conclusion can be drawn from Fig. 12; at high effective pumping speeds, the ratio between the O-atom density at the edge of the discharge chamber and the remote chamber stabilizes and approaches a constant value. For our particular experimental device, this constant value is approximately 20. Any further increase in the effective pumping speed beyond, say 150 m3 h−1, has practically no influence on this ratio. In practice, it means that for each configuration of the connecting tube, an appropriate pumping speed should be selected. There is no need to go to extremes—a reasonable pumping rate would do the job well. The effective pumping speeds in a tokamak are, of course, much higher than those obtained under our experimental conditions. This means that one could afford a much wider connecting tube in real experiments on tokamaks. Considering the conductance of the connecting tube (Fig. 6) and the required pumping speed (Fig. 12), one could estimate that the critical conditions for the optimal transfer of neutral oxygen atoms from the discharge chamber (placed away from the tokamak) to the remote areas of the tokamak where atoms should do their job (removal of hydrogenated carbon deposits) are met if the conductance of the connecting tube is close to the effective pumping speed. This practical consideration should be taken into account when constructing real experiments on tokamaks.
Let us now discuss the behavior of the O-atom density versus pressure and discharge power. The results of systematic measurements are presented in Fig. 8. The O-atom density at first increases with increasing pressure, reaches a maximum, and then decreases with further pressure increase. The increasing density at low pressure is merely an effect on increasing number of oxygen molecules available for dissociation. The number of molecules of course increases linearly with increasing pressure. In the region of increasing O-atom density, the density practically does not depend on the discharge power as long as it is reasonably high. In fact, a “general curve” is observed in Fig. 8. Measurements at any power follow this general curve but deviate from it at a certain pressure. The branching point depends on power, and the pressure at which branching is observed increases monotonously with increasing power. This result reveals an important rule; at a certain pressure, the O-atom density does not depend much on power as long as it is high enough. Any increase in power in this regime has practically no effect on the O atoms density so one does not have to boost power as long as the pressure is low enough to assure for following the general curve.
As the pressure becomes sufficiently high, the O-atom density deviates from the general curve but quickly exhibits a maximum. The maximum shifts to higher pressure as the discharge power is increased. An important conclusion is that at a certain discharge power, an optimal pressure for the highest O-atom density exists. For example, at the power of 1.5 kW the optimal pressure is about 15 Pa, at 3 kW it is almost 30 Pa while at 4 kW it is already 35 Pa. To generalize, the higher the power is, the higher is the pressure required to obtain the maximum O-atom density. Such behavior is explained by the dissociation of oxygen molecules by electron impact in electrode-less RF discharges with predominant H mode. The electrons oscillate in the induced electric field inside the discharge coil. The maximum kinetic energy of the oscillating electrons increases with increasing discharge power. As long as the pressure is low enough, the mean free path of electrons is longer than the oscillation amplitude so the electrons gain the optimal kinetic energy from the induced electric field. At higher pressure, however, the electrons collide with neutral molecules before achieving the optimal energy so their heating is perturbed—they change their direction along the local electric field, so that heating is no longer particularly effective. This effect causes decreasing electron temperature with increasing pressure in the falling portions of the curves presented in Fig. 8. Obviously, a more intense electric field assures better acceleration of electrons and that explains the experimental observation of shifting the maximum of O-atom density towards higher pressure at increasing discharge power.
From upper limits, it is best to increase the discharge power to very high values to obtain the highest O-atom density possible. In practice, however, there are limitations. Most of these arise from high voltages involved when running discharges at high power. It is well known that high-frequency electrode-less discharges are almost perfectly optimized for low powers [19, 20, 21, 22, 23, 24, 25]. The voltage on the RF coil is reasonable low, at a comfortably level of about 500 V. Such systems are suitable for treatment of small samples. However, as mentioned in the Introduction §1, such small discharges are not suitable for large sources of atoms as required for removal of hydrogenated carbon deposits in tokamaks. Scaling up the discharges is not trivial requiring higher voltages to sustain plasmas in large discharge vessels. Voltages should be increased over a kV and this often causes huge problems. A higher voltage results in an increase in the capacitive coupling between the RF coil and any grounded metal objects in the vicinity, including the discharge vessel flanges. Not only the RF power is lost by this capacitive coupling but high-voltage sheaths appear as well. Positive ions are accelerated in such sheaths and cause bombardment of the plasma facing materials and thus sputtering. Sputtered material deposits anywhere in the discharge vessel and forms a layer of foreign material. Such a thin film has a higher coefficient for heterogeneous surface recombination of oxygen atoms than the originally smooth glass surface. This effect leads directly to a loss of O atoms on the surfaces and thus a poor dissociation fraction in the discharge vessel, also similarly reflected in the remote chamber.
Large powers should be therefore avoided. A method by which voltages are maintained at reasonable levels but still preserve plasma homogeneity in the system is the application of two or more parallel coils. This is why we used a double coil as described in the “Experimental Setup”. The impedance of the coil (and the coil voltage) depends on the number of turns. A single-turn “coil”, which is often used in small inductively coupled RF discharges operating in an almost pure H mode, has the lowest voltage but does not allow for creation of homogeneous plasma in large discharge tubes. As mentioned earlier, our discharge tube is two meters long. A reasonably uniform plasma at elevated pressure can only be created by using coils with many turns. Such coils, however, have high impedances and thus very high voltages appear. To minimize the high voltage effects but maintain a uniform plasma, we developed a two parallel coupled coil setup (see “Experimental Setup”). Such a configuration enables reasonable voltage levels to be achieved and a reasonable plasma uniformity.
The dissociation fraction of oxygen molecules in the remote chamber is not great—an order of magnitude of 1 % (see Fig. 9). Taking into account the ratio between the O-atom density at the edge of the discharge and in the remote chamber (Fig. 12), the dissociation fraction in the remote chamber cannot be increased substantially by optimization of the O atom production in the discharge chamber. There is, however, a way of increasing the dissociation fraction (if one really insists on this) by using a mixture of oxygen and argon (or perhaps any other noble gas). The results presented in Fig. 10 clearly show that the dissociation fraction of oxygen molecules could be increased by a factor 1.5 or so solely by replacing about 40 % of oxygen with argon. Otherwise, the dissociation fraction curves (Fig. 9) follow a qualitatively similar behavior as the O-atom density in the remote chamber (Fig. 8) except that the maxima are shifted to somewhat lower pressures. The fact that the dissociation fraction decreases with decreasing pressure in the remote chamber could be attributed to a longer mean free path at lower pressures, a fast diffusion of atoms onto the walls of the connecting tube and the remote chamber, and thus more extensive loss by heterogeneous surface recombination. The recombination coefficient for glass and aluminum has been found to be very low [22, 40, 41] but still high enough to represent the major reason for the O atom loss on the way from the discharge to the remote chambers.
Systematic investigation on an oxygen plasma delivery system for a tokamak focusing on the density of O atoms in the remote chamber has produced important conclusions that are summarized as follows: (1) the O atoms can survive a long path from the discharge chamber to the remote chamber; (2) atom survival is unhindered despite the connecting tube having a number of sharp bends; (3) the most critical parameter governing survival is the effective pumping speed; (4) the optimal O-atom density in the remote chamber depends on the pressure and the discharge power—for each particular discharge power, an optimal pressure should be determined experimentally; (5) effective pumping speed needs not be excessive; (6) a high discharge power is needed to generate large quantities of O atoms and the problems arising from high voltages appearing at high powers could be minimized by using a specific coupling of RF coils and the generator; and (7) the dissociation fraction of O atoms in the remote chamber peaks at a pressure that depends on the discharge power, and can be increased by a factor of 1.5 using an appropriate mixture of argon and oxygen instead of pure oxygen. The results clearly show that, for removal of hydrogenated carbon deposits from remote parts of tokamaks with carbon materials present at the most exposed parts of divertors, a large source of O atoms can be suitably delivered for application in real reactor environments. Preliminary experiments with rather hard hydrogenated carbon deposits presented in this paper indicate that the removal rate at temperatures characteristic for operation of ITER in the first stage is several 10 nm/s which is a suitable value for application of this technology in tokamaks with carbon divertors.
The authors gratefully acknowledge the financial contribution by the European Fusion Development Association (EFDA) through contracts for basic and preferential support as well as the Slovenian Research Agency through contract nos. P2-0082. The operation was also financed in part by the European Union, European Social Fund.
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