Abstract
The issue of quench is related to safety operation of large-scale superconducting magnet system fabricated by cable-in-conduit conductor. A numerical method is presented to simulate the thermal hydraulic quench characteristics in the superconducting Tokamak magnet system. One-dimensional fluid dynamic equations for supercritical helium and the equation of heat conduction for the conduit are used to describe the thermal hydraulic characteristics in the cable -in-conduit conductor. The high heat transfer approximation between supercritical helium and superconducting strands is taken into account due to strong heating induced flow of supercritical helium. The fully implicit time integration of upwind scheme for finite volume method is utilized to discretize the equations on the staggered mesh. The scheme of a new adaptive mesh is proposed for the moving boundary problem and the time term is discretized by the-implicit scheme. It remarkably reduces the CPU time by local linearization of coefficient and the compressible storage of the large sparse matrix of discretized equations. The discretized equations are solved by the IMSL. The numerical implement is discussed in detail. The validation of this method is demonstrated by comparison of the numerical results with those of the SARUMAN and the QUENCHER and experimental measurements.
| Original language | English |
|---|---|
| Pages (from-to) | 985-996 |
| Number of pages | 12 |
| Journal | KSME International Journal |
| Volume | 14 |
| Issue number | 9 |
| DOIs | |
| State | Published - Sep 2000 |
Keywords
- Cable-in conduit-conductors
- Finite volume method of upwind scheme
- Fusion superconducting magnet
- Staggered mesh
- Thermal hydraulic behavior
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