Bulletin of the American Physical Society
51st Annual Meeting of the APS Division of Plasma Physics
Volume 54, Number 15
Monday–Friday, November 2–6, 2009; Atlanta, Georgia
Session UO7: Magneto Inertial Fusion & Neutron Generation |
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Chair: James Degnan, Kirtland AFRL Room: Regency VII |
Thursday, November 5, 2009 2:00PM - 2:12PM |
UO7.00001: Effects of external and self-generated magnetic fields on laser-driven implosions O. Polomarov, P. Chang, O. Gotchev, R. Betti The magnetized laser-driven implosions are studied using ALE hydro-code DRACO coupled with the newly developed MHD block (with anisotropic, \textbf{\textit{B}}-dependent transport coefficients). Considered: i) compression of an externally imposed magnetic field and ii) self-generation of the magnetic field by non-collinear density and pressure gradients. For the first case, it is shown that the moderate external magnetic field of ($<$10 Tesla) can be compressed to hundreds of Mega-Gauss at the implosion stagnation [O. Gotchev et al., submitted to PRL, (2009)]. The field of such amplitude can influence the thermal flux from the target core and results in noticeable effects on the target hydro-dynamics. For the second case, it is shown that the self-generated magnetic field can be amplified to the multi-mega-gauss level at the different implosion stages by at least three MHD-related mechanisms: i) the Tidman instability due to a lateral \textbf{\textit{B}}-dependent heat flux, ii) the Rayleigh-Taylor instability at the ablation front and, iii) the corrugation instability of spherical shock fronts. It is also shown that the magnetic field initially produced at the critical surface significantly reduces the imprinting of laser irradiation non-uniformities onto the ablation surface. [Preview Abstract] |
Thursday, November 5, 2009 2:12PM - 2:24PM |
UO7.00002: Foil Liner Compression of FRCs to Megagauss Fields John Slough, David Kirtley, Chris Pihl, George Votroubek, Richard Milroy, George Marklin The Foil Liner Compression Experiment will explore the metallic liner compression of the FRC where a theta pinch compression coil will be employed to drive a thin foil liner. The intention is to reduce the complexity and enhance the survivability of the apparatus, as well as minimize the kinetic energy required to reach fusion conditions. It is believed that it is possible to accomplish this at sub-megajoule energies. This however will require operation at very small scale. At small scale the implosion speed must be reasonably fast to maintain the magnetized plasma (FRC) equilibrium during compression. These additional considerations imply that a relatively thin liner must be employed. For limited liner kinetic energy, it becomes clear that the thinnest liner imploded to the smallest radius consistent with the requirements for FRC equilibrium lifetime is desired. For the experiments planned, existing facilities for FRC target creation will be adapted for insertion into an aluminum foil liner with a radius of 70 mm and a thickness of 0.1 mm. A key component of this work will be advancement of the numerical codes to provide accurate and predictive capabilities of the plasma/foil liner compression. These efforts will also be discussed. [Preview Abstract] |
Thursday, November 5, 2009 2:24PM - 2:36PM |
UO7.00003: Plasma Liner Formation and Compression Experiments on PLC George Votroubek, John Slough, Chris Pihl, David Kirtley To make fusion practical at small scale, an efficient method for repetitively compressing the FRC to fusion gain conditions is required. A promising approach that is being explored at the MSNW facility employs a plasma shell to radially compress and heat the FRC plasmoid to fusion conditions. The energy that is required for the implosion compression and heating of the FRC plasmoid is derived from both the radial kinetic energy of the plasma liner used to compress it, and the axial kinetic energy of the FRC's motion prior to compression. The design, construction testing of the large array (32) of MPD plasma sources has been completed and initial testing of the liner formation and implosion are underway. Liner masses of 3 mg have been formed in Xenon and have been accelerated to a velocity of 36 km/s employing a theta pinch compression coil at 0.5 T. In these experiments roughly half of the compression bank energy is transferred to the plasma liner. Details of the liner dynamics and future plans for FRC compression with the liner will be discussed. [Preview Abstract] |
Thursday, November 5, 2009 2:36PM - 2:48PM |
UO7.00004: ICF Hybrid Burner Using Tritium-Lean Targets George Miley, Xiaoling Yang, Sung-jin Kim, Heinrich Hora A near-term ICF driven actinide burner has gained much interest.. However, the D-T ICF approach with tritium breeding gives a low support ratio. We propose here using fast ignition of tritium-lean targets to obtain a higher fraction of useful neutrons by reducing tritium-breeding requirements while lowering neutron-induced material damage [1]. This approach appears feasible as simulations show fast ignited tritium-lean targets use only a modest added input-energy over DT targets [2, 3]. Further, discovery of the ``block ignition'' concept is even more encouraging [3]. Thus we suggest the added time to go directly to tritium lean ICF burners (vs. D-T) is minimal. The presentation reviews physics and technology issues for development of a competitive actinide burner.\\[4pt] [1] M. Ragheb, et al., ``Alternate approach to ICF with low tritium inventories and high power densities'', \textit{J. Fus. Energy} \textbf{4, }339-351 (1985).\\[0pt] [2] G. N. Miley, ``Tritium-Lean Fusion Reactors Revisited'', \textit{ ANS TOFE Conference}, San Francisco, CA, Sept. 2008.\\[0pt] [3] G.H. Miley, et al., ``Reduction of Threshold for Laser Fusion Ignition at Nonlinear Force Driven Block Acceleration'', \textit{ANS TOFE Conference}, San Francisco, CA, Sept. 2008 [Preview Abstract] |
Thursday, November 5, 2009 2:48PM - 3:00PM |
UO7.00005: Compact, Energy Efficient Neutron Source: Enabling Technology for Thorium Breeder and Accelerator Transmutation of Waste A. Hershcovitch, W. Horak, B. Johnson, M. Todosow, T. Roser, M. Driscoll A novel neutron source concept, in which a deuterium beam (energy of about 100 keV) is to be injected into a tube filled with tritium gas or tritium plasma, is described. At the opposite end of the tube, the energy of deuterium ions that did not interact is recovered. Be walls of proper thickness will absorb 14 MeV neutrons and release 2 -- 3 lower energy neutrons. Each ion source and tube forms a module. Larger systems can be formed from multiple units. Beam propagation can be further enhanced with vortex-stabilized discharges, electron beams in opposite direction (with energy recovery) or magnetic fields. Deuterium ions propagating through tritium plasma are slowed down and deposit significant energy in the tritium target. Plasma heating results in high temperature electron, thus reducing deuterium ion energy loss. Equilibrium electron temperature exceeding 200 eV can be achieved. Unlike current methods, where accelerator based neutron sources require large amounts of power for operation, this neutron source is compact and can generate neutrons at higher power efficiency. Being modular, the concept can be tested in tabletop experiments. [Preview Abstract] |
Thursday, November 5, 2009 3:00PM - 3:12PM |
UO7.00006: SABR fusion-fission hybrid transmutation reactor design concept Weston Stacey A conceptual design has been developed for a sub-critical advanced burner reactor (SABR) consisting of i) a sodium cooled fast reactor fueled with the transuranics (TRU) from spent nuclear fuel, and ii) a D-T tokamak fusion neutron source based on ITER physics and technology. Subcritical operation enables more efficient transmutation fuel cycles in TRU fueled reactors (without compromising safety), which may be essential for significant reduction in high-level waste repository requirements. ITER will serve as the prototype for the fusion neutron source, which means SABRs could be implemented to help close the nuclear fuel cycle during the 2$^{nd}$ quarter of the century. [Preview Abstract] |
Thursday, November 5, 2009 3:12PM - 3:24PM |
UO7.00007: Nuclear fuel cycle analysis of the SABR fusion-fission hybrid transmutation reactor Chris Sommer, Weston Stacey, Bojan Petrovic Various fuel cycles have been designed and analyzed for the Subcritical Advanced Burner Reactor (SABR). SABR is a sodium cooled fast reactor fueled with transuranics (TRU) from spent fuel of light water reactors and driven by a tokamak fusion neutron source based on ITER physics and technology. SABR employs a four batch fuel cycle using an out-to-in shuffling pattern, with the fuel being reprocessed at the end of each cycle. The reprocessing method assumes recovery rates of 99.9{\%} of the actinides and 0.1{\%} of the fission products remain in the recycled fuel. The reprocessing fuel cycles were analyzed to find an optimal cycle length in terms of burn up, power distribution, and materials limitations. Fuel cycles are analyzed using CEA's ERANOS2.0 code, with fuel residence times limited by radiation damage at 100, 150 and 200 dpa. [Preview Abstract] |
Thursday, November 5, 2009 3:24PM - 3:36PM |
UO7.00008: Dynamical Safety Analysis of the SABR Fusion-Fission Hybrid Reactor Tyler Sumner, Weston Stacey, Seyed Ghiaassian A hybrid fusion-fission reactor for the transmutation of spent nuclear fuel is being developed at Georgia Tech. The Subcritical Advanced Burner Reactor (SABR) is a 3000 MWth sodium-cooled, metal TRU-Zr fueled fast reactor driven by a tokamak fusion neutron source based on ITER physics and technology. We are investigating the accident dynamics of SABR's coupled fission, fusion and heat removal systems to explore the safety characteristics of a hybrid reactor. Possible accident scenarios such as loss of coolant mass flow (LOFA), of power (LOPA) and of heat sink (LOHSA), as well as inadvertent reactivity insertions and fusion source excursion are being analyzed using the RELAP5-3D code, the ATHENA version of which includes liquid metal coolants. [Preview Abstract] |
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