Experimental thermal behaviour of the Toroidal Field Model Coil: Application to ITER TF transient regimes

被引：0

作者：

Nicollet, S ^{[1
]}

Duchateau, JL ^{[1
]}

Fillunger, H ^{[1
]}

Park, SH ^{[1
]}

Zhan, G ^{[1
]}

机构：

[1] CEN Cadarache, EURATOM Assoc, Dept Rech Fus Controlee, F-13108 St Paul Les Durance, France

来源：

ADVANCES IN CRYOGENIC ENGINEERING, VOLS. 49A AND B | 2004年 / 710卷

关键词：

D O I：

暂无

中图分类号：

O414.1 [热力学];

学科分类号：

摘要：

The ITER Toroidal Field (TF) magnet is made of 18 coils. The 7 winding-pack modules constituting their structure, contain each one double pancake Cable-In-ConduitConductor (CICC) inserted in a stainless steel radial plate. The winding pack is enclosed inside a thick stainless steel case. During a safety discharge of the TF system, eddy currents and associated heat generation are induced in the plates and in the case. Such fast discharges have been performed during Phase I and Phase 11 experiment of the Toroidal Field Model Coil (TFMC) tests to investigate heat generation and transfer. Simple models have been developed to predict the behaviour of the coil during these transients. These models have been validated by calorimetric measurements. These models can also be used to estimate the temperature increase of the TF Conductor during a plasma disruption and to investigate whether a quench can happen.

引用

页码：693 / 700

页数：8

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