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Comparisons and analysis on the prototype EU-DEMO TF CICC with Nb<sub>3</sub>Sn cable
Kwon, Soun Pil The Korea Institute of Applied Superconductivity a 2017 한국초전도저온공학회논문지 Vol.19 No.4
European R&D on designing their version of a DEMO fusion tokamak has recently resulted in the testing of a prototype $Nb_3Sn$ Cable-in-Conduit Conductor (CICC) for the DEMO TF coil. The characteristics and reported results of low temperature performance tests with the prototype CICC sample are compared with those from CICC samples incorporating other recent $Nb_3Sn$ cable designs. The EU-DEMO TF CICC prototype shows performance characteristics similar to that of the ITER CS CICC with short twist pitch. This is a first for a CICC sample that does not have a circular cross section. Assessment of its internal magnetostatic self-field suggests that a reduction in the internal self-field due to the rectangular geometry of the EU-DEMO TF CICC prototype compared to one with a circular geometry may have contributed to the performance characteristics showing current sharing temperature ($T_{cs}$) initially increase then stabilize with repeated electromagnetic loading, similarly to ITER CS CICC results. However, constraints on the internal self-field are not a sufficient condition for this $T_{cs}$ characteristic to occur.
Preliminary Performance Test Results of First CICC From Korea Destined for an ITER TF Magnet
Soun Pil Kwon,Soo-Hyeon Park,Stepanov, B.,Bruzzone, P.,Keeman Kim IEEE 2013 IEEE transactions on applied superconductivity Vol.23 No.3
<P>The Republic of Korea is participating in the ITER project to construct and operate the ITER tokamak for the purpose of demonstrating the feasibility of fusion power. ITER Korea, the implementing agency for the Republic of Korea that is procuring items for the ITER project on behalf of the Korean government, has established domestic and international contracts for the procurement of cable-in-conduit conductor (CICC) that will be used in the ITER toroidal field (TF) magnets. The CICC for the ITER TF magnets is made of superconducting and copper strand cable inside a cylindrical stainless steel jacket, and is designed to operate at a nominal peak field of 11.8 T at 4.5 K with 68 kA of nominal operating current. Recently, the first CICC from Korea, which will be installed in an ITER TF magnet, has been manufactured and tested including testing performed on a 4 m sample near ITER operating conditions at the CRPP-EPFL SULTAN facility in Villigen, Switzerland under the coordination of the ITER International Organization. This paper provides a brief description of the CICC along with preliminary results of the tests and the conductor performance characteristics derived from the results.</P>
Overview of Performance Test of Korean CICCs for ITER TF Magnet
Soo-Hyeon Park,Soun Pil Kwon,Won Woo Park,Heekyung Choi,Young Jae Ma,Young Ho Seo,Stepanov, Boris,Bruzzone, Pierluigi Institute of Electrical and Electronics Engineers 2016 IEEE transactions on applied superconductivity Vol.26 No.4
<P>The Korean Domestic Agency (KODA) for the International Thermonuclear Experimental Reactor (ITER) project has taken the responsibility of the procurement of cable-in-conduit conductors for the ITER toroidal field magnet. While procuring 27 conductor unit lengths, which are the Korean sharing, 10 conductors have gone through the superconducting performance test, under low temperature and high magnetic field, as one of the final acceptance tests. The sample assembly and instrumentation of various voltage taps and temperature sensors have been done according to the specified procedure, which had been agreed between domestic agencies and the ITER International Organization. The performance test program, which has also been agreed, was carried out. For the assessment of the current sharing temperature (T-cs), the standard analysis procedure has been adopted. T-cs of all samples, at 68 kA and a background field of 10.78 T, after 1000 cyclic current loads are well above the acceptance criterion. By analyzing the electric field as a function of temperature, the effective strain (epsilon(eff)) and transition index (n-value) were reduced, and the behavior of epsilon(eff) will be discussed in terms of the electromagnetic load, i.e., I x B. The effective strain was compared with the physical strain and results with a numerical simulation.</P>
Overview of Conductor Production for ITER Toroidal Field Magnet in Korea
Soo-Hyeon Park,Soun Pil Kwon,Won Woo Park,Heekyung Choi,Young Jae Ma,Young Ho Seo,Ki Hong Sim,Pyeong Yeol Park,Jun-Seg Lee,Il-Young Han,Sung Chan Kang,Dong Hee Lee,Turtu, S.,Di Zenobio, A.,Quagliata, IEEE 2014 IEEE transactions on applied superconductivity Vol.24 No.3
<P>The ITER toroidal field (TF) conductor is made up of superconducting Nb<SUB>3</SUB>Sn and copper strands assembled into a multistage, rope-type cable inserted into a conduit of butt-welded stainless steel jacket sections. For the ITER Project, the Korean Domestic Agency (KODA) took the responsibility of the procurement of 27 superconducting conductors for the ITER TF magnets. After concluding the Procurement Arrangement (PA) with the ITER International Organization in May 2008, KODA has been implementing the PA through four major industrial contracts: (1) Nb<SUB>3</SUB>Sn strand, (2) cable, (3) stainless steel jacket sections, and (4) jacketing. Prior to the production of conductors required for the TF coils, one 760-m-long copper dummy conductor and one 100-m-long superconducting conductor were fabricated for manufacturing process qualification. As of June 2013, 16 TF conductors were successfully manufactured. The full-size conductor performance tests in the SULTAN facility yielded very high performance. This article describes the technical requirements of the TF conductor and how KODA has been manufacturing the conductors with a high-level quality assurance/quality control system. It also presents the results of acceptance tests, including those of the SULTAN test.</P>
Conductor Performance Qualification of TFKO3 Sample for ITER TF Magnet
Soo-Hyeon Park,Soun Pil Kwon,Keeman Kim,Stepanov, B.,Bruzzone, P. IEEE 2012 IEEE transactions on applied superconductivity Vol.22 No.3
<P>Two identical conductor samples were fabricated from 110 m length cable prepared for qualification of the manufacturing process for Phase II procurement of ITER TF conductor. Superconducting strand characteristics, cabling specifications, and the stainless steel jacket sections are described. Sample assembly and instrumentation of various voltage taps and temperature sensors have been prepared according to specified procedures for conductor performance qualification. The performance test program which was agreed to by the SULTAN working group was applied to the conductor samples. To assess the current sharing temperature , standard analysis procedures were adopted. The of both samples at 68 kA with a background field of 10.78 T after a 1000 cyclic load are well above the acceptance criteria. Behavior of individual “star” voltage taps which are located at different positions and which are possible origins of rather large discrepancies in the of identical samples is discussed. The effective strain and the transition index of the samples are obtained from the experimental data.</P>
Soo-Hyeon Park,Jun Young Kim,Won Woo Park,Heekyung Choi,Young Jae Ma,Soun Pil Kwon,Keeman Kim,Sung Chan Kang,Dong Hee Lee Institute of Electrical and Electronics Engineers 2012 IEEE transactions on applied superconductivity Vol.22 No.3
<P>While the manufacturing of superconducting CICC (cable in conduit conductor) and winding conductors into winding packs for ITER TF magnets, cold work is unavoidably applied on the jacketing tube. This article investigates the effect of plastic deformation on low temperature mechanical and magnetic properties of austenite 316LN stainless steel tube for ITER TF conductor. To simulate the manufacturing process of TF magnet, tubes were compacted, extended to 2.5% in longitudinal direction and heat treated. After each step, specimens were sectioned using wire cutting EDM, and tensile tests at 4 K, magnetic susceptibility measurements, and hardness tests have been carried out on those specimens. Remarkable reductions of elongation at failure have been observed as the amount of cold work is increased through compaction and extension. Further, correlations among results of tensile tests, magnetic susceptibility measurements and hardness tests are presented.</P>