Conceptual design of the China fusion power plant FDS-II

Abstract As one of the series of fusion system design concepts developed in China, the fusion power plant FDS-II, is designated to exploit and evaluate the potential lucrativity of using fusion energy for generating electricity based on the advanced plasma parameters, which can be extrapolated from the successful operation of ITER. Two options of specific liquid LiPb blanket concepts for FDS-II have been proposed, i.e., the He/LiPb Dual-cooled Lithium Lead (DLL) breeder blanket (∼700 °C coolant outlet temperature) and the He-cooled Quasi-Static Lithium Lead (SLL) breeder blanket (∼450 °C coolant outlet temperature), with RAFM steel as the structural material. In this paper, an overview of the FDS-II conceptual design will be presented and a series of performance analyses are summarized. Further R&D needs will be specified.

[1]  Kikuchi Mitsuru,et al.  The advanced SSTR , 2000 .

[2]  L. Giancarli,et al.  Status of the design and performances of the WCLL test blanket module for ITER-FEAT , 2002 .

[3]  Huang Qun-ying Activation analysis and waste management for dual-cooled lithium lead breeder (DLL) blanket of the fusion power reactor FDS-II , 2005 .

[4]  P. Sardain,et al.  The European power plant conceptual study: Helium-cooled lithium–lead reactor concept , 2006 .

[5]  Mark S. Tillack,et al.  Combination of a self-cooled liquid metal breeder blanket with a gas turbine power conversion system , 1998 .

[6]  Ulrich Fischer,et al.  The EU advanced dual coolant blanket concept , 2002 .

[7]  Qunying Huang,et al.  Progress in development of China Low Activation Martensitic steel for fusion application , 2007 .

[8]  E. Diegele,et al.  Materials and design of the European DEMO blankets , 2004 .

[9]  Yican Wu,et al.  Design status and development strategy of China liquid lithium-lead blankets and related material technology , 2007 .

[10]  Yican Wu,et al.  Conceptual design activities of FDS series fusion power plants in China , 2006 .

[11]  Fds Team An integrated multi-functional neutronics calculation and analysis code system:VisualBUS , 2007 .

[12]  U. Fischer,et al.  Conceptual design of the dual-coolant blanket in the frame of the EU power plant conceptual study , 2003 .

[13]  D. P. Luigi,et al.  DEMO and fusion power plant conceptual studies in Europe , 2006 .

[14]  Liao He-qin R&D status of China low activation martensitic steel , 2007 .

[15]  Steven J. Zinkle,et al.  An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design , 2006 .

[16]  Yican Wu,et al.  Progress in fusion-driven hybrid system studies in China , 2002 .

[17]  Hu Li-qin Economic analysis of the fusion-driven subcritical system , 2004 .

[18]  Liqin Hu,et al.  Conceptual design of the fusion-driven subcritical system FDS-I , 2006 .

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

[20]  Chen Hong-li Conceptual design study on the fusion power reactor FDS-II , 2005 .

[21]  Shinya Konishi,et al.  A high temperature blanket concept for hydrogen production , 2008 .

[22]  Mark S. Tillack,et al.  Design and material issues for high performance SiCf/SiC-based fusion power cores , 2001 .

[23]  J. F. Briesmeister MCNP-A General Monte Carlo N-Particle Transport Code , 1993 .

[24]  Yves Poitevin,et al.  The EU advanced lead lithium blanket concept using SiCf/SiC flow channel inserts as electrical and thermal insulators , 2001 .

[25]  J. G. Delene,et al.  Cost Assessment of a Generic Magnetic Fusion Reactor , 1986 .

[26]  Yves Poitevin,et al.  HCLL TBM for ITER-design studies , 2005 .

[27]  Yasushi Seki Overview of the Japanese fusion reactor studies programme , 2000 .

[28]  Liu Song-lin Structural design and analysis of dual-cooled lithium-lead blanket module for the fusion power reactor FDS-II , 2005 .

[29]  Wu Yican,et al.  Integral Data Test of HENDL1.0/MG and VisualBUS with Neutronics Shielding Experiments (I) , 2004 .

[30]  Mark S. Tillack,et al.  Blanket system selection for the ARIES-ST , 2000 .

[31]  Mark S. Tillack,et al.  Advanced power core system for the ARIES-AT power plant , 2006 .

[32]  Jingshan Jiang,et al.  Comparison analysis of 1D/2D/3D neutronics modeling for a fusion reactor , 2008 .

[33]  Wu Yi-can Thermal-hydraulics design and analysis on the dual-cooled lithium-lead breeder blanket for the fusion power reactor FDS-II , 2005 .