7 results
Search Results
2. JC(B, T, ϵ) Parameterization for the ITER Nb3Sn Production.
- Author
-
Bottura, Luca and Bordini, Bernardo
- Subjects
- *
MAGNETIC properties of superconductors , *PARAMETER estimation , *SCALING laws (Statistical physics) , *ELECTRIC currents , *NIOBIUM , *TIN compounds - Abstract
A number of models for the critical surface of Nb3 Sn, and in general A15 superconductors, have been developed in the past years. This paper compares the most common parameterizations using consistent notation. Although the parameterizations appear dissimilar at first sight, they are in reality all based on a fit of the normalized pinning force vs. the reduced field, and have similar scalings for the critical field and critical temperature based on a Unified Scaling Law. In this paper we take the various parameterizations as a basis for a generic scaling proposed for the characterization and production follow-up of the ITER Nb3 Sn strands. The accuracy of the scaling is estimated using the fitting residuals on various sets of Ic (B, T, ϵ) data available in literature. We discuss the results, and give our view of the work towards a unified, practical parameterization. [ABSTRACT FROM AUTHOR]
- Published
- 2009
- Full Text
- View/download PDF
3. Test Results From the PF Conductor Insert Coil and Implications for the ITER PF System.
- Author
-
Bessette, D., Bottura, Luca, Devred, A., Mitchell, N., Okuno, K., Nunoya, Y., Sborchia, C., Takahashi, Y., Verweij, A., Vostner, A., Zanino, R., and Zapretilina, E.
- Subjects
- *
DIRECT currents , *ALTERNATING currents , *LORENTZ force , *ELECTRICAL conductors , *MAGNETIC properties of superconductors - Abstract
In this paper we report the main test results obtained on the Poloidal Field Conductor Insert coil (PFI) for the International Thermonuclear Experimental Reactor (ITER), built jointly by the EU and RF ITER parties, recently installed and tested in the CS Model Coil facility, at JAEA-Naka. During the test we (a) verified the DC and AC operating margin of the NbTi Cable-in-Conduit Conductor in conditions representative of the operation of the ITER PF coils, (b) measured the intermediate conductor joint resistance, margin and loss, and (c) measured the AC loss of the conductor and its changes once subjected to a significant number of Lorentz force cycles. We compare the results obtained to expectations from strand and cable characterization, which were studied extensively earlier. We finally discuss the implications for the ITER PF system. [ABSTRACT FROM AUTHOR]
- Published
- 2009
- Full Text
- View/download PDF
4. Electromagnetic Analysis of the Voltage-Temperature Characteristics of the ITER TF Conductor Samples.
- Author
-
Breschi, Marco, Ribani, Pier Luigi, and Bellina, Fabrizio
- Subjects
- *
ELECTRIC conduits , *ELECTRICAL conductors , *ELECTROMAGNETIC measurements , *ELECTRIC cables , *COMPUTER simulation , *THERMAL properties ,HEATING effects of electric currents - Abstract
The measurement of the current sharing temperature of a Cable in Conduit Conductor is a complex task. The voltage traces measured on the conduit (jacket) of these conductors during tests, give V∙I characteristics that significantly differ from the typical transition from the superconducting to the resistive state measured on single strands. In these measurements, after an initial ramping of the transport current up to the test value, the temperature is increased by steps until the resistive transition occurs. However, even in the first phase of the current ramping, when the cable is still fully or almost superconductive, early voltages are measured along the jacket at different angular positions around the cable. In particular, this was observed in the ITER TF conductors recently tested in the SULTAN facility at Villigen PSI, Switzerland. These samples showed significant ramps of voltages taken in the proximity of the joints and terminations. The present paper gives a possible qualitative and quantitative explanation for this mechanism. Numerical simulations are also shown which reproduce the scattering of the voltages measured around the jacket at a given location, showing the effect of the voltage taps position along the jacket in a six sub-cable model. [ABSTRACT FROM AUTHOR]
- Published
- 2009
- Full Text
- View/download PDF
5. Safety Analysis of the 70 kA ITER HTS Current Lead Demonstrator.
- Author
-
Helter, R.
- Subjects
- *
HIGH temperature superconductors , *ELECTRIC currents , *SHUNT electric reactors , *HELIUM , *NUCLEAR fusion - Abstract
For the superconducting magnet system of the International Thermonuclear Experimental Reactor, ITER, 60 current leads for a total current of more than 2500 kA are needed. The use of High Temperature Superconductor current leads (HTS-CL) will reduce the resultant large refrigerator load considerably. Within the EU Fusion Technology Programme, the Forschungszentrum Karlsruhe and CRPP have developed and built a 70 kA HTS-CL demonstrator optimized for 50 K Helium operation. In 2004-2005, the CL was successfully tested with 50 K as well as 80 K Helium, and finally with LN2. In the meantime, ITER has decided to use HTS-CLs for the magnet system and China has taken the responsibility to provide the sc feeders for ITER including the current leads. In this paper, the performance of a 70 kA HTS-CL in fault conditions will be analysed using the FZK-CRPP demonstrator as a model. In particular, the quench performance and the safety behavior in case of a loss-of-flow accident (LOFA) will be described and an extrapolation of the leads performance in real ITER conditions will be given. Finally the effect of different shunt materials is discussed. [ABSTRACT FROM AUTHOR]
- Published
- 2009
- Full Text
- View/download PDF
6. R&D Towards HTS Current Leads for ITER.
- Author
-
Bauer, Pierre, Bi, Yanfang, Cheng, Anyi, Devred, Arnaud, Ding, Kaisong, Huang, Xiongyi, Lu, Kun, Mitchell, Neil, Sahu, Ananta K., Shen, Guang, Song, Yuntao, and Zhou, Tingzhi
- Subjects
- *
SUPERCONDUCTING magnets , *SUPERCONDUCTORS , *ELECTRICITY experiments , *SUPERCONDUCTIVITY - Abstract
The ITER Organization (10) and the Institute of Plasma Physics at the Chinese Academy of Sciences (ASIPP) are jointly developing the 68 kA current leads using High Temperature Superconductors for the superconducting Toroidal Field (TF) magnet system of the International Thermonuclear Experimental Reactor, ITER. The proposed design consists of a conventional helium cooled heat exchanger operating between 65 K and 320 K and an HTS module covering the low temperature end using Bi-2223 tapes. The first HTS current lead prototypes will be tested in the EAST tokamak facility at ASIPP. This paper discusses the design of the first, 68 kA, TF HTS lead, which is the main emphasis of this first stage of the ITER current lead development program. [ABSTRACT FROM AUTHOR]
- Published
- 2009
- Full Text
- View/download PDF
7. 2014 IEEE compound semiconductor IC symposium.
- Subjects
- *
INTEGRATED circuits conferences - Abstract
Describes the above-named upcoming conference event. May include topics to be covered or calls for papers. [ABSTRACT FROM PUBLISHER]
- Published
- 2014
- Full Text
- View/download PDF
Discovery Service for Jio Institute Digital Library
For full access to our library's resources, please sign in.