Each of our rod designs are intended to explore different ablative scenarios in order to benchmark existing ablation models.
Details of our project deliverables and experimental results are described below.
Our designed rods are inserted into the DiMES assembly before being placed inside the tokamak for experiments. The different pieces of the DiMES assembly are labeled in the picture on the right. For reference, the fully assembled DiMES assembly from the top of the rods to the bottom of the base is approximately 4.5 inches, while the rods protract ~0.6 inches above the DiMES head.
(from left to right)
Concave
This design allows for exploring the possibility of plasma detachment due to neutrals trapped in the cavity. It was of particular interest to investigate whether the cavity "traps'' a pocket of less energetic neutral molecules that serve to protect the main body from high heat flux through increased radiation as well as a reduction in parallel plasma pressure.
Wedge
The high velocities found in the divertor region of the tokamak prompted the idea of integrating a sharp-nosed, aerodynamic design to evaluate the ablation rate in comparison to the blunt geometry. The sharp-nosed design is a triangular rod with a 45-degree angle of incidence to the incoming flow. The triangular profile mimics hypersonic vehicle profiles which is relevant due to the velocities experienced inside the tokamak, which are on the order of km/s.
Cylindrical (Reduced Diameter)
A variation of the cylindrical rod was designed with a diameter that was reduced by .005 in to allow for the application of a silicon carbide (SiC) coating. SiC is of interest to both the aerospace community and the nuclear fusion community due to its anti-oxidizing properties. Adding a layer of this material allows an investigation into whether or not SiC can protect the underlying substrate (ATJ graphite) from oxidation and assist in retaining its material properties.
Cylindrical
The blunt geometry is a simple cylindrical rod with a rounded end to reduce heat concentration found at sharp edges. The symmetric shape of this rod also makes it the most robust design. The blunt geometry rod is frequently used in ablation experiments, which allows for comparison to other ablation studies.
All measurements in inches unless otherwise specified
One of the most undesirable complications during the ablation experiment would be if the casing holding the rods were to crack. The most likely cause for such cracking would be via the thermal expansion of the rod’s base causing stresses on the DiMES casing.
From this, it is expected that the rod's base will expand approximately 0.022 mm due to the exposure, but to increase the factor of safety and ensure that the DiMES port casing won't crack, the rod was undersized by 0.15 mm. As a result of this adjustment, a pin was designed, to secure the orientation of the rod by being inserted between the rod and casing to prevent rotation due to the incoming plasma flow.
All measurements in inches unless otherwise specified
In order to limit the amount of impurities introduced into the plasma within the tokamak, the volume of the rods that would be exposed to the plasma needed to be no greater than 2 cm^3. The exposed portion of the rod is everything above the 0.50 inch height specified above.
ATJ grade graphite was chosen as the base material of every rod, because of its high thermal shock resistance, high thermal conductivity, low thermal expansion, and uniform properties, which makes it a robust choice of material that is resistant to the high heat fluxes anticipated during the experiments. The thermal properties provide even ablation rates and resistance to breaking off during the experiment. In addition, carbon-based materials are suitably used as plasma facing materials and in thermal protection systems. ATJ graphite properties are also well documented in DIII-D’s experimental past, as the panels that make up the reaction chamber of DIII-D itself are entirely constructed out of ATJ graphite. This provides controlled upper limits for how much of the carbon impurities can be introduced into the plasma discharge, due to the ablation.
Silicon carbide (SiC) is another material worth exploring that is of interest to both the aerospace and the nuclear fusion communities. SiC is useful in aerospace applications due to its anti-oxidizing properties. Carbon oxidizes at high temperatures, which reduces its strength and could decrease the performance of spacecraft heat shields. Adding a layer of SiC over a core of carbon-based material, such as ATJ graphite, helps protect the substrate from oxidation and assists retention of its material properties. In addition, coating ATJ carbon rods with a thin layer of SiC (~30 μm thick) ensures that the maximum amount of Si deposited into the DIII-D plasma during experiments represents a low risk of disrupting the discharge. This thin film of silicon carbide was applied to the ATJ graphite rod through a process called sputter deposition.
ATJ Grade Graphite:
All components made from ATJ Graphite
Rods
Casing
Spacer
Material Properties
Very fine-grained
Uniform thermal properties
Low thermal expansion
High thermal conductivity
Resistance to thermal shock
Silicon Carbide (SiC):
Application of 30 microns coating to the reduced diameter cylindrical rod.
Material Properties
Protects substrate from Oxidation
Low thermal expansion
Well Documented and Uniform properties
The heat flux incident to the surface of the rod was estimated. The rods, which will extend approximately 2 cm into the plasma, will experience a wide range of heat fluxes over their length, ranging from around 27.8 MW/m^2 at the top to around 7.79 MW/m^2 at the bottom. Based on the results from a transient thermal analysis on ANSYS, a 2 cm tall rod tip would experience a temperature of approximately 4100°C at the end of a 4-second exposure. The temperature distributions are shown in the images below. The time series of the temperature reveals that the rod reaches the carbon sublimation temperature of 3542°C, or approximately 3800K at approximately 1.2 seconds. After this point, it is assumed that the ablation cloud shields the rod from further incoming plasma flux and therefore maintains this temperature while ablating for the remaining 2.8 seconds of the total 4 second exposure.
An analysis was conducted to determine the magnitude of the current-induced stresses on the rod after the onset of ablation. Due to the presence of a magnetic field in the tokamak, a JxB force is induced and needs to be accounted for in our stress analysis of the carbon rods. SolidWorks Simulation was used to predict the maximum current the rod can withstand before failing. The worst-case scenario that did not produce stresses greater than the 25.5 MPa or 3.7 ksi tensile strength of ATJ graphite was found to be 565 Amps. In our analysis, it was determined that the other two rod designs would be able to withstand this current worst-case scenario without failing. However, the forces produced by the 565 Amp current yielded a factor of safety not much higher than one. The original experiment plan was to expose the 2 cm length of rod out of the DiMES port, but for cautionary measures for tokamak discharges, the lengths came down to 1.5 cm in exposed lengths. This decision was made in order to increase the safety factor with regards to the current-induced forces, as a shorter rod results in a smaller torque.
The mass loss rate of the carbon sample was calculated as the ratio of heat flux incident to the surface of the sample to carbon heat of ablation. Two different models were considered, one by Park and another by Matsuyama, which were previously used to calculate carbon ablation during the Galileo probe entry into Jupiter's atmosphere. Thompson scattering measurements of electron temperature, electron density, and incident heat flux to the sample surface during DIII-D discharge 170837 are used as inputs for both models. As the thermal analysis determined that the rod would ablate for ~2.8 seconds, it was expected that 73 mg or ~8% of the total rod will ablate over the exposure time. This suggests that the carbon rod samples in our experiment will only partially ablate if exposed to discharge conditions similar to shot 170837 for exposure times 3-4s as shown in the figure below.
Mass loss recession rate predicted using Thompson scattering data from DIII-D discharge 170837 and (left) Park model and (right) Matsuyama model. Locations of the plasma separatrix (bold black lines) and several constant magnetic flux surfaces in the Scrape-off Layer and Private Flux regions are overlaid for reference
Experimental Day 1 - Head 2
Testing Rods Structural Integrity
Lower Heat Flux ( ~1 Mega Watts)
Silicon Carbide (SiC) Coating lost
No Measurable Ablation Observed
Experimental Day 2 - Head 5
Full Plasma Blast
Higher Heat Flux (~2.7 Mega Watts)
Silicon Coating Lost
Measurable Ablation Observed
Rows specify different DiMES heads. Columns specify rod position in each head, labeled in yellow in the photographs.
1st Day: No Ablation
Lower heat fluxes experienced led to little mass lost. The mass lost on the 1st day was due to the silicon carbide flaking off during the experiment, not because of ablation.
2nd Day: Significant Ablation
Our rods successfully ablated on the 2nd day of experiments, and with the data we are able to test existing ablation models, in hopes for future researchers to expand upon scientific inquiry.