Progress of the Engineering Design for the HT-7U Steady-State Superconducting Tokamak

Journal Article · Mon Jul 15 04:00:00 EDT 2002 · Fusion Science and Technology

OSTI ID:20845846

Songtao, Wu; Weiyue, Wu; Yinnian, Pan; Damao, Yao; Ziying, Liao; Yanfang, Bi; Zhuoming, Chen; Baozeng, Li; Yuntao, Song; Wenge, Chen; Jin, Fang; Peide, Weng; Daming, Gao; Jiangang, Li; Yuanxi, Wan; Honqiang, Li; Wanjiang, Pan; Junling, Chen; Jing, Wei ^[1]

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1. Institute of Plasma Physics (China)

The HT-7U superconducting (SC) tokamak will have a long-pulse capability, a flexible poloidal field (PF) system, and auxiliary heating and current drive systems, and it will be able to accommodate divertor heat loads that make it an attractive test for the development of advanced tokamak operating modes. The greatest progress has been made on the engineering design of the HT-7U SC tokamak device, including the calculation and simulation of plasma shaping and control of the PF system as well as calculation and analyses of stress and deformation distribution on the main components caused by dynamic electromagnetic forces, vacuum pressure, temperature differences, etc. Significant research and development progress on the design and the testing of the cable-in-conduit conductor of the toroidal field and PF has been made. A test facility system for the SC magnets of HT-7U has been set up and operated.

• OSTI ID: 20845846
• Journal Information: Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 1 Vol. 42; ISSN 1536-1055
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
AUXILIARY HEATING
COMPUTERIZED SIMULATION
CONTROL
DEFORMATION
DESIGN
DISTRIBUTION
DIVERTORS
ENGINEERING
HEATING LOAD
HT-7U TOKAMAK
PLASMA
PLASMA SIMULATION
PULSES
STEADY-STATE CONDITIONS
STRESSES
SUPERCONDUCTING MAGNETS
TEST FACILITIES
TESTING