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| Content Provider | IEEE Xplore Digital Library |
|---|---|
| Author | Ilyin, Yu. Bessette, D. Zapretilina, E. Luongo, C. Simon, F. Byung Su Lim Mitchell, N. |
| Copyright Year | 2002 |
| Abstract | Recent design changes to the ITER Poloidal Field (PF) coils and PF conductor layout have been implemented to give a greater operational window for low li (self-inductance) plasmas during burn, extend the operating window for plasmas with currents above 15 MA, and improve the plasma vertical stability control. In addition, the PF and CS (Central Solenoid) operating window has been updated leading to higher currents and peak fields in some of the PF coils. Altogether, this results in higher heat generation in the PF conductors due to AC losses. To confirm that the range of heat loads is acceptable for the PF conductors, a time-dependent thermo-hydraulic analysis of the PF coils has been performed with a model based on the GANDALF code. The deposited heat due to AC losses in the conductors, thermal radiation, thermal conduction, and nuclear heating are given as input data. The results show a moderate impact on minimum temperature margin of the PF conductors during the baseline scenario, stemming from the design modifications. |
| Sponsorship | Council on Superconductivity Appl. Superconductivity Conference Inc MIT |
| Starting Page | 415 |
| Ending Page | 418 |
| Page Count | 4 |
| File Size | 387449 |
| File Format | |
| ISSN | 10518223 |
| Volume Number | 20 |
| Issue Number | 3 |
| Language | English |
| Publisher | Institute of Electrical and Electronics Engineers, Inc. (IEEE) |
| Publisher Date | 2010-06-01 |
| Publisher Place | U.S.A. |
| Access Restriction | One Nation One Subscription (ONOS) |
| Rights Holder | Institute of Electrical and Electronics Engineers, Inc. (IEEE) |
| Subject Keyword | Performance analysis Conductors Superconducting coils Superconducting cables Plasma stability Plasma temperature Power cables Niobium compounds Titanium compounds thermo-hydraulic analysis AC loss cable-in-conduit conductor ITER magnet NbTi strand poloidal field coils temperature margin |
| Content Type | Text |
| Resource Type | Article |
| Subject | Condensed Matter Physics Electronic, Optical and Magnetic Materials Electrical and Electronic Engineering |
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