7 results on '"Schaubel Kurt"'
Search Results
2. Testing of the ITER Central Solenoid Modules
- Author
-
Martovetsky, Nicolai, primary, Freudenberg, Kevin, additional, Rossano, Graham, additional, Khumthong, Kenneth, additional, Norausky, Nikolai, additional, Ortiz, Ed, additional, Piec, Zbigniew, additional, Schaubel, Kurt, additional, Sheeron, Jeffrey, additional, Kaskin, Gordon, additional, Smith, John, additional, Bonifetto, Roberto, additional, Zanino, Roberto, additional, Zappatore, Andrea, additional, Schild, Thierry, additional, Gauthier, Florent, additional, Jong, Cornelis, additional, Ilyin, Yuri, additional, Myatt, Leonard, additional, Cochran, Kristen, additional, Breschi, Marco, additional, and Langhorn, Alan, additional
- Published
- 2022
- Full Text
- View/download PDF
3. Factory Acceptance Test of 50-kA HTS Current Leads for the ITER CS Magnet Test Application
- Author
-
Qingqing Du, Li Jun, Sikui Yu, Yuntao Song, Liuwei Xu, Kun Lu, Xiongyi Huang, Ran Qingxiang, Tingzhi Zhou, Bo Li, Piec Zbigniew, Jing Kaiming, Chenglian Liu, Han Quan, Kaizhong Ding, Ke Zhang, and Schaubel Kurt
- Subjects
Resistive touchscreen ,Materials science ,Mass flow ,Nuclear engineering ,Solenoid ,Superconducting magnet ,Flange ,Condensed Matter Physics ,01 natural sciences ,010305 fluids & plasmas ,Electronic, Optical and Magnetic Materials ,Acceptance testing ,Magnet ,0103 physical sciences ,Electrical and Electronic Engineering ,Current (fluid) ,010306 general physics - Abstract
The Institute of Plasma Physics, Chinese Academy of Sciences was contracted by General Atomics Company to develop a superconducting feeder system containing a pair of 50-kA high-temperature superconducting (HTS) current leads for ITER central solenoid magnet test. These HTS current leads (HTSCL) are based on the previous ITER lead design experiences. However, the vertical assembly design of HTSCL which is different from ITER's horizontal assembly causes the water leakage in the insulation flange during the initial phase. Some improvements were recognized and expected to avoid the potential risk for further prototypes and series production of ITER leads. Some development experiences are shared in this paper. The HTS current leads contain BiSCCO AgAu matrix tapes to minimize the heat load to 4.5 K end. Its resistive part is cooled by 50-K helium. In the HTS part, the conduction cooling is adopted. The HTS current leads were integrated in the feeder system to perform 4.5-K full current test. The factory acceptance test was implemented to verify the high-voltage and thermodynamic performances. The maximum current of 55 kA was achieved. The test indicates that the helium mass flow consumption is 3.3 g/s per lead and the loss of flow accident time is approximate to 10 min at the nominal current with the stoppage of 50-K helium. The insulation flange passed the high-voltage test of 15 kV, while the leakage current is less than 1 mA after the improvement. More detailed test results will be shown in this paper.
- Published
- 2018
4. The 5 K Heat Load Test of GA Feeder for ITER CS Magnet Test Application
- Author
-
Schaubel Kurt, Jing Kaiming, Chenglian Liu, Tingzhi Zhou, Qingqing Du, Kun Lu, Sikui Yu, Bo Li, Kaizhong Ding, Ke Zhang, Piec, Yuntao Song, and Zbigniew
- Subjects
Materials science ,Busbar ,Electromagnetic coil ,Nuclear engineering ,Shield ,Magnet ,0103 physical sciences ,Thermal ,Duct (flow) ,010306 general physics ,01 natural sciences ,Volumetric flow rate ,Electronic circuit - Abstract
The GA Feeder is a superconducting feeder system, which connects from the Room Temperature (RT) power supply system to the 4.5 K busbar of the magnet, used for Iter Central Solenoid magnet test at General Atomics Company in U.S.A. This system is make up of 3 parts: Coil Terminal Box (CTB), Feeder duct (FD), In Chamber Feeder-through (ICF), containing a pair of 52 kA High Temperature Current leads (HTSCL), thermal shield, busbars, joint boxes, pipes and other components. It has been developed and cold tested at the Institute of Plasma Physics, Chinese Academy of Sciences, and the 5K heat load test was performed in Dec. 2015. The requirement of overall heat load 68 W is a big challenge, and many efforts were took to achieve the required value, such as reduce the inlet pressure of the whole system as much as possible, minimize the flow rate of different cooling circuits, a dedicated program was developed to online calculated the density and the heat load to help analyzing the heat load of the system. This paper will present the 5K heat load measurement of this system.
- Published
- 2018
5. Superconducting Feeder System for ITER Central Solenoid Module Final Test Facility
- Author
-
Piec, Zbigniew, primary, Ding, Kaizhong, additional, Kun, Lu, additional, Langhorn, Alan, additional, Lloyd, S., additional, Salazar, Erica, additional, Schaubel, Kurt, additional, Smith, John, additional, and Zhou, Tingzhi, additional
- Published
- 2018
- Full Text
- View/download PDF
6. Factory Acceptance Test of 50-kA HTS Current Leads for the ITER CS Magnet Test Application.
- Author
-
Kaizhong Ding, Tingzhi Zhou, Kun Lu, Qingqing Du, Bo Li, Sikui Yu, Xiongyi Huang, Chenglian Liu, Ke Zhang, Kaiming Jing, Qingxiang Ran, Quan Han, Jun Li, Liuwei Xu, Yuntao Song, Piec Zbigniew, and Schaubel Kurt
- Subjects
MAGNETS ,MAGNETISM ,MAGNETIC fields ,SUPERCONDUCTORS ,SOLENOIDS - Abstract
The Institute of Plasma Physics, Chinese Academy of Sciences was contracted by General Atomics Company to develop a superconducting feeder system containing a pair of 50-kA high-temperature superconducting (HTS) current leads for ITER central solenoid magnet test. These HTS current leads (HTSCL) are based on the previous ITER lead design experiences. However, the vertical assembly design of HTSCL which is different from ITER's horizontal assembly causes the water leakage in the insulation flange during the initial phase. Some improvements were recognized and expected to avoid the potential risk for further prototypes and series production of ITER leads. Some development experiences are shared in this paper. The HTS current leads contain BiSCCO AgAu matrix tapes tominimize the heat load to 4.5 K end. Its resistive part is cooled by 50-K helium. In the HTS part, the conduction cooling is adopted. The HTS current leads were integrated in the feeder system to perform 4.5-K full current test. The factory acceptance test was implemented to verify the highvoltage and thermodynamic performances. The maximum current of 55 kA was achieved. The test indicates that the helium mass flow consumption is 3.3 g/s per lead and the loss of flow accident time is approximate to 10 min at the nominal current with the stoppage of 50-K helium. The insulation flange passed the high-voltage test of 15 kV, while the leakage current is less than 1 mA after the improvement. More detailed test results will be shown in this paper. [ABSTRACT FROM AUTHOR]
- Published
- 2018
- Full Text
- View/download PDF
7. Superconducting Feeder System for ITER Central Solenoid Module Final Test Facility.
- Author
-
Zbigniew Piec, Kaizhong Ding, Lu Kun, Langhorn, Alan, Lloyd, S., Salazar, Erica, Schaubel, Kurt, Smith, John, and Tingzhi Zhou
- Subjects
SUPERCONDUCTORS ,SOLENOIDS ,CRYOGENICS ,ELECTRIC insulators & insulation ,HELIUM - Abstract
General Atomics has commissioned the final test facility at the central solenoid module (CSM) manufacturing site in Poway, CA, USA. The facility includes a number of critical subsystems including the feeder system (FS), supplied by the Institute of Plasma Physics Chinese Academy of Science (ASIPP), that connects the test chamber to the cryogenic and electrical systems. It includes a coil termination box, high-temperature superconducting current leads, and a feeder duct. The FS carries the current (50 kA) and supercritical helium (4.5 K, 5.5 bara) to the CSM and its supporting structure, while monitoring and controlling the temperature, pressure, flow, and voltage drop through all elements of the superconducting components. It functions as an integral part of the system to rapidly (6-s decay time) dissipates 1-GJ energy stored in the coils, and to protect the cryogenic system. The system is complex, requiring multidisciplinary engineering including: high-temperature superconductivity, cryogenic-temperatures (77, 50, and 4.5 K), high vacuum (1.0×10
-5 Pa), redundant quench detection (voltage, temperature), high-voltage insulation (15 kV), low thermal loads (70 W), lowelectrical joint resistance (2 nΩ), Paschen testing, high-voltage signal measurements, and high-current electronics. The system presented significant challenges for design and analysis, complex manufacturing assembly processes, measurement and control, and stringent quality and safety requirements. [ABSTRACT FROM AUTHOR]- Published
- 2018
- Full Text
- View/download PDF
Catalog
Discovery Service for Jio Institute Digital Library
For full access to our library's resources, please sign in.