Calculations of pressure drop and mass flow distribution in the toroidal field model coil of the ITER project

Cryogenics

Volumn 40, Issue 8-10, 2000, Pages 569-575

  Nicollet, S ^a   Duchateau, J L ^a   Fillunger, H ^b   Martinez, A ^a  

^a IRFM   (France)

^b EFDA CLOSE SUPPORT UNIT   (Germany)

Author keywords

Cable in conduit conductors; Forced flow; Fusion magnets

Indexed keywords

CORRELATION METHODS; EXPERIMENTAL REACTORS; FRICTION; FUSION REACTORS; HELIUM; NITROGEN; PRESSURE DROP; REYNOLDS NUMBER; SUPERCONDUCTING CABLES; SUPERCONDUCTING MAGNETS; SUPERCRITICAL FLUIDS;

CABLE IN CONDUIT CONDUCTORS (CICC); SUPERCONDUCTING TOROIDAL FIELD MODEL COIL (TFMC);

SOLENOIDS;

EID: 0034456096     PISSN: 00112275     EISSN: None     Source Type: Journal    
DOI: 10.1016/s0011-2275(01)00014-5     Document Type: Article

References (7)

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3. Katheder H. Optimum thermohydraulic operation regime for cable in conduit superconductors (CICS). In: Proceedings of the 15th international cryogenic engineering conference, Genova, Italy. 1994. p. 595-98.
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5. Hamada K, Anghel A, Smith S, et al. Thermal and hydraulic measurement in the ITER quell experiments. Adv Cry Eng 1998;43A:197-200.
6. Michael PC. Coil geometry and shimming requirements. MIT plasma science and fusion center private communication. Cambridge (MA), USA, February 2000.
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