Analysis of thermal-hydraulic gravity/buoyancy effects in the testing of the ITER poloidal field full size joint sample (PF-FSJS)
The PF-FSJS is a full-size joint sample, based on the NbTi dual-channel cable-in-conduitconductor (CICC) design currently foreseen for the International ThermonuclearExperimental Reactor (ITER) Poloidal Field coil system. It was tested during the summer of 2002 in the Sultan facility of CRPP at a background peak magnetic field of typically 6 T. It includes about 3 m of two jointed conductor sections, using different strands but with identical layout. The sample was cooled by supercritical helium at nominal 4.5-5.0 K and 0.9-1.0 MPa, in forced convection from the top to the bottom of the vertical configuration. A pulsed coil was used to test AC losses in the two legs resulting, above a certain input power threshold, in bundle helium backflow from the heated region. Here we study the thermalhydraulics of the phenomenon with the M&M code, with particular emphasis on the effects of buoyancy on the helium dynamics, as well as on the thermal-hydraulic coupling between the wrapped bundles of strands in the annular cable region and the central cooling channel. Both issues are ITER relevant, as they affect the more general question of the heat removal capability of the helium in this type of conductors.
Bibliographic Reference: An oral paper given at: 2003 Cryogenic Engineering Conference (CEC) and International Cryogenic Materials Conference (ICMC) Held at: Anchorage, Alaska, USA, September 22-26, 2003
Availability: Available from Association EURATOM-CEA, Département de Recherches sur la Fusion Contrôlée, CEA Cadarache, F-13108 St Paul-Lez-Durance, France Tel: (+33) 4 42 25 70 01; Fax: (+33) 4 42 25 64 21 E-mail: email@example.com
Record Number: 200417324 / Last updated on: 2004-01-07
Original language: en
Available languages: en