Evaluation of CFETR key parameters with different scenarios using system analysis code

Abstract This paper presents a system analysis on both phases of China Fusion Engineering Test Reactor (CFETR) under the same structure of toroidal field coil with a magnetic field on axis of 6–7 T and device size of major radius of R ∼ 6 m. Phase I is designed with moderate gain aimed at exploring steady-state scenarios with DEMO relevant plasmas. One operating mode with higher magnetic field and conservative physics is presented, which could serve as a backup CFETR baseline in case of shortfall in physics performance. Phase II targets high gain with power plant relevant requirements and objectives, including more than 1 GW of fusion power, high fusion gain for DEMO validation and more ambitious assumptions based on advanced physics. A system analysis code, General Atomics System Code (GASC) [R. Stambaugh, V. Chan, et al., Fusion nuclear science facility candidates, Fusion Sci. Technol., 59 (2001) 279–307] is used to evaluate key parameters of scenarios for both phases.

[1]  Lei Liu,et al.  Concept Design and Analysis of CFETR Vertical Instability Control Using Passive Plates and In-Vessel Coils , 2015 .

[2]  T. C. Luce,et al.  Electron cyclotron current drive efficiency in general tokamak geometry , 2003 .

[3]  Jie Zhang,et al.  Magnetic fusion development for global warming suppression , 2010 .

[4]  T. Fujita,et al.  Chapter 2: Plasma confinement and transport , 2007 .

[5]  A. E. Costley,et al.  On the power and size of tokamak fusion pilot plants and reactors , 2015 .

[6]  J. A. Leuer,et al.  Fusion Nuclear Science Facility Candidates , 2011 .

[7]  B. Wan,et al.  Physics Design of CFETR: Determination of the Device Engineering Parameters , 2014, IEEE Transactions on Plasma Science.

[8]  A. Polevoi,et al.  Chapter 1: Overview and summary , 2007 .

[9]  R. D. Stambaugh,et al.  THE SPHERICAL TOKAMAK PATH TO FUSION POWER , 1998 .

[10]  C. Giroud,et al.  Scaling of density peaking in H-mode plasmas based on a combined database of AUG and JET observations , 2007 .

[11]  Minami Yoda,et al.  The ARIES Advanced and Conservative Tokamak Power Plant Study , 2014 .

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

[13]  E. Joffrin,et al.  Chapter 6: Steady state operation , 2007 .

[14]  R. D. Stambaugh,et al.  A fusion development facility on the critical path to fusion energy , 2011 .

[15]  L. L. Lao,et al.  Physics Basis of a Fusion Development Facility Utilizing the Tokamak Approach , 2010 .

[16]  Peng Fu,et al.  Concept Design of CFETR Tokamak Machine , 2014, IEEE Transactions on Plasma Science.

[17]  David Ward,et al.  On the physics guidelines for a tokamak DEMO , 2013 .

[18]  J. A. Leuer,et al.  Evaluation of CFETR as a Fusion Nuclear Science Facility using multiple system codes , 2015 .

[19]  Charles G. Bathke,et al.  Systems analysis in support of the selection of the ARIES-RS design point , 1997 .