NDLI: DC resistance and eddy current losses in the ITER conductor joint

Content Provider	IEEE Xplore Digital Library
Author	Myatt, R.L. Pillsbury Jr., R.D.
Copyright Year	2002
Abstract	The central solenoid (CS) and the toroidal field (TF) coils of the International Thermonuclear Experimental Reactor (ITER) are wound from superconducting (SC) Nb/sub 3/Sn Cable-in-Conduit-Conductor (CICC). Electrical joints are an important aspect of the coil design, since local heating from resistive losses can drive the superconductor into a less stable regime and possibly initiate a quench. A good joint design will satisfy the broadest requirement which is to minimize the power dissipation during normal coil operations. This can be achieved by satisfying two, more specific, and in some ways, conflicting requirements: (1) to provide a low DC resistance, and (2) to minimize the effects of Joule heating from eddy currents induced by transient magnetic fields. This paper presents a finite element analysis of the latest conductor joint concept and evaluates its electromagnetic characteristics with respect to these two requirements. The analysis extends the usual practice of representing the presence of superconductors with surface conditions by explicitly modeling the last stage of the twisted cable. Although certain modeling approximations limit the accuracy of the results, some valuable insights are gained, such as which approximations cannot be made, and the effects of various design details on the DC joint resistance and Joule heating.<>
Sponsorship	Council on Superconductivity Appl. Superconductivity Conference Inc MIT
Starting Page	996
Ending Page	999
Page Count	4
File Size	455764
File Format	PDF
ISSN	10518223
Volume Number	5
Issue Number	2
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	1995-06-01
Publisher Place	U.S.A.
Access Restriction	One Nation One Subscription (ONOS)
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Eddy currents Conductors Superconducting coils Superconducting cables Resistance heating Magnetic analysis Electric resistance Solenoids Inductors Wounds
Content Type	Text
Resource Type	Article
Subject	Condensed Matter Physics Electronic, Optical and Magnetic Materials Electrical and Electronic Engineering

Sl.	Authority	Responsibilities	Communication Details
1	Ministry of Education (GoI), Department of Higher Education	Sanctioning Authority	https://www.education.gov.in/ict-initiatives
2	Indian Institute of Technology Kharagpur	Host Institute of the Project: The host institute of the project is responsible for providing infrastructure support and hosting the project	https://www.iitkgp.ac.in
3	National Digital Library of India Office, Indian Institute of Technology Kharagpur	The administrative and infrastructural headquarters of the project	Dr. B. Sutradhar bsutra@ndl.gov.in
4	Project PI / Joint PI	Principal Investigator and Joint Principal Investigators of the project	Dr. B. Sutradhar bsutra@ndl.gov.in Prof. Saswat Chakrabarti will be added soon
5	Website/Portal (Helpdesk)	Queries regarding NDLI and its services	support@ndl.gov.in
6	Contents and Copyright Issues	Queries related to content curation and copyright issues	content@ndl.gov.in
7	National Digital Library of India Club (NDLI Club)	Queries related to NDLI Club formation, support, user awareness program, seminar/symposium, collaboration, social media, promotion, and outreach	clubsupport@ndl.gov.in
8	Digital Preservation Centre (DPC)	Assistance with digitizing and archiving copyright-free printed books	dpc@ndl.gov.in
9	IDR Setup or Support	Queries related to establishment and support of Institutional Digital Repository (IDR) and IDR workshops	idr@ndl.gov.in

Design and Test Results of Joints for ITER TF Feeder Current Leads and Superconducting Busbars

Strand resistance distribution in an improved full size joint for the ITER conductors

The 50 kA Superconducting Transformer for Testing ITER CC Conductors Short Sample

Sensitivity of Nb/sub 3/Sn ITER conductor design to selected parameters

Inter-Strand Resistance in the Termination of ITER Conductors

From Short Sample to Coil DC Superconductor Performance: ITER Central Solenoid Model Coil (CSMC) vs. Good Joint (GJ) Sample

Predictive Analysis of the ITER Poloidal Field Conductor Insert (PFCI) Test Program

Analysis of losses in ITER joints in a varying parallel field

Tests and analysis of quench propagation in the ITER toroidal field conductor insert

DC resistance and eddy current losses in the ITER conductor joint

Similar Documents

Design and Test Results of Joints for ITER TF Feeder Current Leads and Superconducting Busbars

Strand resistance distribution in an improved full size joint for the ITER conductors

The 50 kA Superconducting Transformer for Testing ITER CC Conductors Short Sample

Sensitivity of Nb/sub 3/Sn ITER conductor design to selected parameters

Inter-Strand Resistance in the Termination of ITER Conductors

From Short Sample to Coil DC Superconductor Performance: ITER Central Solenoid Model Coil (CSMC) vs. Good Joint (GJ) Sample

Predictive Analysis of the ITER Poloidal Field Conductor Insert (PFCI) Test Program

Analysis of losses in ITER joints in a varying parallel field

Tests and analysis of quench propagation in the ITER toroidal field conductor insert

DC resistance and eddy current losses in the ITER conductor joint