THERMOHYDRAULICS OF CICCS WITH CENTRAL COOLING PASSAGE

被引:7
作者
BOTTURA, L
机构
[1] The NET Team, D-85748 Garching
关键词
D O I
10.1109/77.402655
中图分类号
TM [电工技术]; TN [电子技术、通信技术];
学科分类号
0808 ; 0809 ;
摘要
The cable-in-conduit conductors for ITER will have a ''central cooling hole'', a low impedance flow channel whose purpose is to decrease the pressure drop per unit length. The helium flow and the response to temperature transients of such an arrangement has unique features compared to those of the simpler CICC's without central cooling hole. The purpose of this paper is to discuss these features and to propose a model for the description of the compressible thermohydraulics of the ITER conductors. Some typical applications of the model proposed (transient cooling of a conductor length in a magnet, quench evolution) are also shown as an example.
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收藏
页码:745 / 748
页数:4
相关论文
共 8 条
[1]  
ANGHEL A, 1994, 18TH S FUS TECHN KAR
[2]  
ARP V, 1978, P SUP MHD MAGN DES C
[3]   QUENCH ANALYSIS OF LARGE SUPERCONDUCTING MAGNETS .1. MODEL DESCRIPTION [J].
BOTTURA, L ;
ZIENKIEWICZ, OC .
CRYOGENICS, 1992, 32 (07) :659-667
[4]  
BOTTURA L, 1993, NET NR082138B REP
[5]   REDUCING QUENCH PRESSURE BY PERFORATING THE JACKET OF A CABLE-IN-CONDUIT SUPERCONDUCTOR [J].
DRESNER, L .
CRYOGENICS, 1993, 33 (10) :958-961
[6]  
GOUTHIER A, 1994, CENG SBT9407 INT REP
[7]   A COMPUTATIONAL QUENCH MODEL APPLICABLE TO THE SMES CICC [J].
LUONGO, CA ;
CHANG, CL ;
PARTAIN, KD .
IEEE TRANSACTIONS ON MAGNETICS, 1994, 30 (04) :2569-2572
[8]   CONDUCTOR DESIGNS FOR THE ITER TOROIDAL AND POLOIDAL MAGNET SYSTEMS [J].
MITCHELL, N .
IEEE TRANSACTIONS ON MAGNETICS, 1994, 30 (04) :1602-1608