Article

Modeling of thermal-hydraulic effects of AC losses in the ITER Central Solenoid Insert Coil using the M&M code

Dipt. di Energetica, Politecnico, Torino, Italy
IEEE Transactions on Appiled Superconductivity (impact factor: 1.04). 07/2003; DOI:10.1109/TASC.2003.812687 pp.1424 - 1428
Source: IEEE Xplore

ABSTRACT During 2000, AC losses and the effects of possible ramp-rate limitation (RRL) were investigated on the International Thermonuclear Experimental Reactor (ITER) Central Solenoid Insert Coil (CSIC), at JAERI Naka, Japan. The CSIC was mounted inside the bore of the ITER Central Solenoid Model Coil (CSMC), at the maximum field of about 13 T and experiencing the largest magnetic field variations. The thermal-hydraulic response of the coil to different transport current scenarios was assessed by measuring the temperature increase and pressurization of the supercritical helium (SHe) coolant, together with the evolution of the mass-flow rate. Here we implement in the M&M code a detailed general model of AC losses, which is being validated for the first time. The resulting tool is then applied to the analysis of two CSIC tests, with different ramp-up of the transport current followed by the same dump, and used to qualitatively assess the major thermal-hydraulic effects of AC losses in the coil.

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  • Article: Inductively driven transients in the CS Insert Coil (II): Quench tests and analysis
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    ABSTRACT: The CS Insert Coil (CSIC), a well-instrumented 140 m long Nb3Sn solenoid wound one-in-hand and installed in the bore of the CS Model Coil, was tested during the summer of 2000 at JAERI Naka, Japan, within the framework of the International Thermonuclear Experimental Reactor large projects [1]. The maximum transport current in the CSIC was 40 kA and the peak background field was 13 T. The coils were cooled by forced flow HeI nominally at 4.5 K and 0.6 MPa. An inductive heater was used to test stability and quench of the CSIC. In this second of two companion papers we concentrate on the analysis of quench initiation and propagation, based on the study of heater calibration and conductor stability presented in the first paper [2]. The initiation and propagation of an inductively driven quench was tested here for the first time in a two-channel Nb3Sn conductor, for different transport currents, delay times of the dump, and temperature margins, and a selection of the corresponding results will be presented and discussed. We use the Mithrandir code [3] to analyze this problem and compare the simulation with the experimental results for the evolution of resistive voltage and quench propagation speed, of peak temperature and pressure, and of inlet and outlet mass-flow rate. © 2002 American Institute of Physics.
    AIP Conference Proceedings. 05/2002; 613(1):423-430.
  • Progress of the ITER central solenoid model coil program. H Tsuji . 2001. Nucl. Fusion 41 645-651.
  • First test results for the ITER central solenoid model coil. T Kato . 2001. Fus. Eng. Des 56-57.

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Keywords

AC losses
 
detailed general model
 
different ramp-up
 
different transport current scenarios
 
International Thermonuclear Experimental Reactor
 
ITER Central Solenoid Model Coil
 
JAERI Naka
 
Japan
 
largest magnetic field variations
 
M&M code
 
mass-flow rate
 
possible ramp-rate limitation
 
qualitatively
 
supercritical helium
 
temperature increase
 
thermal-hydraulic response
 
transport current