The dynomak: An advanced spheromak reactor concept with imposed-dynamo current drive and next-generation nuclear power technologies

Abstract A high-β spheromak reactor concept has been formulated with an estimated overnight capital cost that is competitive with conventional power sources. This reactor concept utilizes recently discovered imposed-dynamo current drive (IDCD) and a molten salt (FLiBe) blanket system for first wall cooling, neutron moderation and tritium breeding. Currently available materials and ITER-developed cryogenic pumping systems were implemented in this concept from the basis of technological feasibility. A tritium breeding ratio (TBR) of greater than 1.1 has been calculated using a Monte Carlo N-Particle (MCNP5) neutron transport simulation. High temperature superconducting tapes (YBCO) were used for the equilibrium coil set, substantially reducing the recirculating power fraction when compared to previous spheromak reactor studies. Using zirconium hydride for neutron shielding, a limiting equilibrium coil lifetime of at least thirty full-power years has been achieved. The primary FLiBe loop was coupled to a supercritical carbon dioxide Brayton cycle due to attractive economics and high thermal efficiencies. With these advancements, an electrical output of 1000 MW from a thermal output of 2486 MW was achieved, yielding an overall plant efficiency of approximately 40%.

[1]  M. J. Driscoll,et al.  ASSESSMENT OF GAS COOLED FAST REACTOR WITH INDIRECT SUPERCRITICAL CO 2 CYCLE , 2006 .

[2]  T. Terai,et al.  Control of molten salt corrosion of fusion structural materials by metallic beryllium , 2009 .

[3]  Richard N. Christensen,et al.  Investigation of High-Temperature Printed Circuit Heat Exchangers for Very High Temperature Reactors , 2009 .

[4]  A. C. Hossack,et al.  Sustained spheromaks with ideal n = 1 kink stability and pressure confinement , 2014 .

[5]  L. Bromberg,et al.  Options for the use of high temperature superconductor in tokamak fusion reactor designs , 2001 .

[6]  R. Klueh,et al.  A potential new ferritic/martensitic steel for fusion applications , 2000 .

[7]  L. L. Lao,et al.  The ARIES-AT advanced tokamak, Advanced technology fusion power plant , 2006 .

[8]  L. Bromberg,et al.  ARIES-AT magnet systems , 2006 .

[9]  M. Sugihara,et al.  Analysis of separatrix plasma parameters using local and multi-machine databases 1 Work supported by , 1998 .

[10]  A. Muhsin.  Chemical Vapor Deposition of Aluminium Oxide (Al 2 O 3 ) and Beta Iron Disilicide (β-FeSi 2 ) Thin Films , 2007 .

[11]  Alumina Thin Films : From Computer Calculations to Cutting Tools , 2008 .

[12]  Vaclav Dostal,et al.  A supercritical carbon dioxide cycle for next generation nuclear reactors , 2004 .

[13]  W. T. Hamp,et al.  Temperature and density characteristics of the Helicity Injected Torus-II spherical tokamak indicating closed flux sustainment using coaxial helicity injection , 2008 .

[14]  Minami Yoda,et al.  The ARIES-CS Compact Stellarator Fusion Power Plant , 2008 .

[15]  S. Orimo,et al.  Advanced neutron shielding material using zirconium borohydride and zirconium hydride , 2009 .

[16]  Laila A. El-Guebaly,et al.  Prospects for pilot plants based on the tokamak, spherical tokamak and stellarator , 2011 .

[17]  R. L. Hagenson,et al.  Steady-State Spheromak Reactor Studies , 1985 .

[18]  A. Sagara,et al.  Progress in Flibe Corrosion Study toward Material Research Loop and Advanced Liquid Breeder Blanket , 2008 .

[19]  George Marklin,et al.  Imposed-dynamo current drive , 2012 .

[20]  B. P. Duval,et al.  Inter-machine comparison of intrinsic toroidal rotation in tokamaks , 2007 .