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c e,ash =c1-2kBTiτEaΨ+1 . (4) 0 c2m −2 1 3~2 applicable solution due to their simplicity of setup is Inertial Electrostatic Confinement (IEC). This technology offers high energy density in small and light reactors, however no breakeven is expected. But due to the design simplicity and scalability, development was still pursued and research done over decades aimed to increase the fusion rates as much as possible. The simplest setup was thought up in [29]: A spherical, concentric and strong negatively biased grid is placed in a grounded, evacuated, spherical chamber (Figure 10). Figure 10: scheme IEC device The grid is the cathode, the chamber wall the anode. The chamber is flooded with fuel. Ions are generated glow discharge and then accelerated to the grid center as a point of stable equilibrium. While the majority of ions do not take part in fusion processes, occasional events may occur if the ions’ energy is sufficient. The reason for starting this venture at IRS is that it is believed IEC to be one of the most promising concepts for the next generation of electric propulsion with high specific impulses. That means an IEC setup can also be operated in ranges where no fusion processes occur. Ions will be accelerated into the center of the cathode grid and will be trapped there until a hole in the potential surface of the cathode grid allows them to escape [26, 30, 31]. These thrusters can be compared to conventional ion thrusters. But it also seems promising technology for Isp’s in the range of e.g. the DS4G [32] or higher. Since it is feasible to accelerate ions to an energy that is enough to allow for particles to fuse, it may also be possible to use the high kinetic energy of ions to generate thrust instead. Moreover the extracted ion beam is a reference case for PICLAS, a code in development at IRS, IAG (both University of Stuttgart) and IHM (Forschungszentrum Karlsruhe). PICLAS aims at simulating highly rarefied plasmas as in PPT, by joining Particle-In-Cell (PIC) with DSMC and Fokker-Planck [33]. If a plasma beam with very high ion velocities can be extracted, a third interesting aspect is the potential application for simulation of high ener- getic radiation. IRS is co- In this equation, c0 is the speed of light, mpyr the product mass yield per reaction, Ψ the product particle multiple and ~τEa the ratio of ash to energy confinement time. The Boltzmann constant is noted kB. The thrust calculates from Fash = mpyr Rik ce,ash (5) using the reaction rate Rik. The thrust efficiency ηTH can be approximated by the ratio of product to reactant density. In working gas drives (WGD), the power losses of the plasma are partly recovered by the coolant/propellant (c/pant). These parts sum up to PTwg. The exhaust velocity is 1 Advanced Plasma (Propulsion) Concepts at IRS 0pyr P −22 c =c1-T,wg +1. (6) 0dt The mass flow of the injected c/pant is noted dmo/dt and needs to assure the necessary cooling of the system. Both system concepts call for subsystems such as the reactors hardware, i.e. the first wall, a blanket which has to be porous in case of WGDs magnets assuring the plasma confinement and a cryo system providing operational temperatures of the magnets. Moreover, there have shields to protect the vessel against harmful radiation and there have to be radiators since the spatial vacuum eliminates waste heat disposal by convection and conduction leaving radiation the only resort. Note that the recovery of waste heat for propulsive means in WGD will lead to a considerably diminished radiator size compared to AD and therefore better propulsion system mass MP. Hydrogen is destined to be used as c/pant for its excellent caloric and propulsive properties. As for the fusion fuel, in general four reactant couplings are considered: D-T, the “classic” fusion reaction considered for terrestrial power generation, and the three advanced couples D-3He, p-11B and 3He-3He. The major advantage the advanced couples promise, are a considerable reduction in neutron radiation and hence lightweight shields. However, investigations at IRS [21] showed that only D-3He is worthwhile as a fuel. Typical propulsive data is documented in table 1. e,wg 0c2dm wg System Ti / keV 22 22 90 90 165 165 B / T 3 3 14 14 106 106 P / W 3.0 e 6 5.3 e 8 7.8 e 7 1.9 e 9 5.1 e 10 1.8 e 11 F / N 2.8 ηTH / % 1 94 4 91 26 93 MP / kg 4.8e5 4.6e5 1.7e5 1.0e5 1.0e7 3.2e6 ε/% τ/d 99.94 2700 3.43 220 ce / m/s 2.2 e 6 6.0e3 1.8e5 5.1 e 6 30.7 1.8e5 2.0e4 6.0e6 1.7e4 2.8e4 1.3e7 plasma, B magnetic containment) - 3He-3He systems do not ignite. D-T - AD D-T - WGD D-3He - AD D-3He - WGD p-11B - AD p-11B - WGD Table 1: Propulsive characteristics of MCFP systems (generic system, 10m3 of 99.85 477 35.69 20 99.62 160 18.42 80 5. Inertial Electrostatic Confinement: Status The most common fusion based setups, TOKAMAK based reactors as ITER or inertial confinement fusion as in NIF, require huge, heavy and complex structures. A more operating with Baylor University in developing a facility for environmental simulation of complex dusty using an inductively heated plasma generator [34]. The IEC test stand is likely to provide ions with energies in the range of natural plasmas and hitherto only insufficiently simulated. 4PDF Image | ADVANCES IN APPLIED PLASMA SCIENCE 2011
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