Shuangsong Du

Conceptual design and analysis of CFETR magnets

CFETR (China Fusion Engineering Test Reactor) is a test reactor which shall be constructed by National Integration Design Group for Magnetic Confinement Fusion Reactor of China. The Reactor has the equivalent scale compared with ITER, but has the complementary function to ITER. CFETR is a demonstration of long pulse or steady-state operation with duty cycle time not less than 0.3~0.5 and the full cycle of tritium self-sustained with TBR not less than 1.2. The magnets design of CFETR is based on the ITER magnet technology. This paper describes a conceptual design and analysis of the CFETR magnets. The constant tension toroidal field coil and three different magnetic equilibrium shapes are present in this paper.

Engineering design of the HELIMAK device

The HELIMAK experiment will provide a simplified magnetic geometry for study of magnetized turbulence, and control of some experimental parameters including flows. By allowing current to flow between the top and bottom boundaries, this magnetic configuration has equilibrium. Because the configuration also matches that found in tokamaks when initial ionization is produced by radiation at the electron cyclotron frequency, there is a sound experimental basis. HELIMAK would provide a test of the flow-shear stabilization mechanism. The HELIMAK device would consist of a vacuum chamber (VC), a toroidal field magnets system and a vertical field magnets system with supports structure. The magnet system and the VC of HELIMAK have been calculated and designed in detail.

Design and structure analysis of the HT-7U vacuum vessel

The vacuum vessel of the HT-7U superconducting tokamak has a full welded structure with double wall which will be filled with borated water is used for neutron shielding, non-circular cross-section is used for plasma elongating, horizontal and vertical ports are used for diagnosing, vacuum pumping, plasma heating and plasma current driving, etc. The vacuum vessel consists of 16 segments. It will be baked out at 250 °C and plasma facing components (PFCs) baked out at 350 °C to get a cleaning wall. When the machine is in operation, hot wall (vacuum vessel wall is around 100 °C and first wall is around 150 °C) and cold wall (vacuum vessel wall and first wall is in normal equilibrium temperature) are both considered. The stress caused by thermal deformation and electromagnetic (EM) loads caused by 1.5 MA plasma disrupt in 3.5 T magnetic field are important in the design of the HT-7U vacuum vessel and PFCs. Finite element method was accepted for structure analysis of the vacuum vessel.

Preliminary Stability Analysis of the CFETR Central Solenoid Conductors

Abstract A Central Solenoid (CS) conductor layout has been tentatively decided during the conceptual design phase of the Chinese Fusion Engineering Testing Reactor (CFETR). To check the validity of the conductor layout, stability analysis must be performed against the working condition of the conductors. We constructed a superconducting critical surface of the strands used in the CS conductors and then calculated the current sharing temperature of the conductors under the most stringent working condition envisioned with the operation parameters. We further analyzed the energy margin by simulating the quenching behavior with the GANDALF code upon disturbances of different durations and lengths representative of a mechanical disturbance and plasma disruption. The analysis results give preliminary estimation of conductor stability for further improvement of the design.