Toroidal Plasma Thruster for Deep Space Flights

A conceptual, theoretical assessment of using the toroidal fusion reactor, tokamak, for deep space interplanetary and interstellar missions is presented. Toroidal thermonuclear fusion reactors, such as tokamaks and stellarators, are unique for space propulsion, allowing a design with the magnetic configuration localized inside the toroidal magnetic field coils. Plasma energetic ions, including charged fusion products, can escape such closed configuration at certain conditions as a result of vertical drift in the toroidal rippled magnetic field. Escaping particles can be used for direct propulsion (because toroidal drift is directed one way vertically) or to create and heat externally confined plasma, so that the latter can be used for propulsion. In contrast to other fusion concepts proposed for space propulsion, this concept utilizes the natural drift motion of charged particles out of the closed magnetic field configuration. Also, using deuterium-tritium (D-T) plasma is a novel way to use fusion neutrons with the energy of 14 MeV for direct propulsion (neutron rocket) for out of solar system missions. A special design of the blanket of the reactor allows neutrons to escape the device in a preferable direction. This provides a direct (partial) conversion of fusion energy into thrust.

[1]  David Buden,et al.  Space nuclear power , 1985 .

[2]  D. L. Morgan.  Concepts for the design of an antimatter annihilation rocket , 1982 .

[3]  Yueng Kay Martin Peng,et al.  The physics of spherical torus plasmas , 2000 .

[4]  Terry Kammash.  Fusion energy in space propulsion , 1995 .

[5]  Stanley K. Borowski,et al.  A spherical torus nuclear fusion reactor space propulsion vehicle concept for fast interplanetary piloted and robotic missions , 1999 .

[6]  Y. Tatematsu,et al.  Progress in High Density Experiments with Potential Confinement on GAMMA 10 , 2001 .

[7]  E. B. Hooper,et al.  Plasma detachment from a magnetic nozzle , 1991 .

[8]  R. White,et al.  Confinement of high energy trapped particles in tokamaks , 1981 .

[9]  A. I. Morozov,et al.  Motion of Charged Particles in Electromagnetic Fields , 1966 .

[10]  P. M. Ryan,et al.  Initial Physics Results From the National Spherical Torus Experiment , 2001 .

[11]  R. Aymar,et al.  ITER-FEAT - the future international burning plasma experiment - present status , 2000 .

[12]  L. Zakharov,et al.  Magnetic propulsion of intense lithium streams in a tokamak magnetic field. , 2003, Physical review letters.

[13]  R. J. Hawryluk,et al.  Results from D—T experiments on TFTR and implications for achieving an ignited plasma , 1998, Philosophical Transactions of the Royal Society of London. Series A: Mathematical, Physical and Engineering Sciences.

[14]  Conway,et al.  H-Mode operation in the START spherical tokamak , 2000, Physical review letters.

[15]  J. M. Diamond.  Propulsion system , 1983 .

[16]  S. J. Zweben,et al.  Measurements of DT alpha particle loss near the outer midplane of TFTR , 1995 .

[17]  Alexander N. Karpushov,et al.  High Pressure Plasma Confinement and Stability Studies in Gas Dynamic Trap , 2001 .

[18]  M. Kissick,et al.  Radial electric field required to suppress ion temperature gradient modes in the Electric Tokamak , 1999 .

[19]  T. Kenneth Fowler,et al.  Space Propulsion by Fusion in a Magnetic Dipole , 1992 .