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- 검색키워드
- 저자 : Sborchia, C. (검색결과 3 건)
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ITER vacuum vessel structural analysis completion during manufacturing phase
Martinez, J.M.,Alekseev, A.,Sborchia, C.,Choi, C.H.,Utin, Y.,Jun, C.H.,Terasawa, A.,Popova, E.,Xiang, B.,Sannazaro, G.,Lee, A.,Martin, A.,Teissier, P.,Sabourin, F.,Caixas, J.,Fernandez, E.,Zarzalejos, North-Holland 2016 Fusion engineering and design Vol.109 No.1
Some years ago, analyses were performed by ITER Organization Central Team (IO-CT) to verify the structural integrity of the ITER vacuum vessel baseline design fixed in 2010 and classified as a Protection Important Component (PIC). The manufacturing phase leads the ITER Organization domestic agencies (IO-DA) and their contracted manufacturers to propose detailed design improvements to optimize the manufacturing or inspection process. These design and quality inspection changes can affect the structural margins with regards to the Codes&Standards and thus oblige to evaluate one more time the modified areas. This paper proposes an overview of the additional analyses already performed to guarantee the structural integrity of the manufacturing designs. In this way, CT and DAs have been strongly involved to keep the considerable margins obtained previously which were used to fix reasonable compensatory measures for the lack of In Service Inspections of a Nuclear Pressure Equipment (NPE).
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Preparation of the ITER poloidal field conductor insert (PFCI) test
Zanino, R.,Egorov, S.,Kim, K.,Martovetsky, N.,Nunoya, Y.,Okuno, K.,Salpietro, E.,Sborchia, C.,Takahashi, Y.,Weng, P.,Bagnasco, M.,Richard, L.S.,Polak, M.,Formisano, A.,Zapretilina, E.,Shikov, A.,Veder IEEE 2005 IEEE transactions on applied superconductivity Vol.15 No.2
The Poloidal Field Conductor Insert (PFCI) of the International Thermonuclear Experimental Reactor (ITER) has been designed in the EU and is being manufactured at Tesla Engineering, UK, in the frame of a Task Agreement with the ITER International Team. Completion of the PFCI is expected at the beginning of 2005. Then, the coil shall be shipped to JAERI Naka, Japan, and inserted into the bore of the ITER Central Solenoid Model Coil, where it should be tested in 2005 to 2006. The PFCI consists of a NbTi dual-channel conductor, almost identical to the ITER PF1 and PF6 design, ∼45 m long, with a 50 mm thick square stainless steel jacket, wound in a single-layer solenoid. It should carry up to 50 kA in a field of ∼6 T, and it will be cooled by supercritical He at ∼4.5 K and ∼0.6 MPa. An intermediate joint, representative of the ITER PF joints and located at relatively high field, will be an important new item in the test configuration with respect to the previous ITER Insert Coils. The PFCI will be fully instrumented with inductive and resistive heaters, as well as with voltage taps, Hall probes, pick-up coils, temperature sensors, pressure gauges, strain and displacement sensors. The test program will be aimed at DC and pulsed performance assessment of conductor and intermediate joint, AC loss measurement, stability and quench propagation, thermal-hydraulic characterization. Here we give an overview of the preparatory work toward the test, including a review of the coil manufacturing and of the available instrumentation, a discussion of the most likely test program items, and a presentation of the supporting modeling and characterization work performed so far.
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Manufacturing progress on the first sector and lower ports for ITER vacuum vessel
Ahn, H.J.,Kim, H.S.,Kim, G.H.,Park, C.K.,Hong, G.H.,Jin, S.W.,Lee, H.G.,Jung, K.J.,Lee, J.S.,Kim, T.S.,Won, J.G.,Roh, B.R.,Park, K.H.,Sa, J.W.,Choi, C.H.,Sborchia, C. North-Holland 2016 Fusion engineering and design Vol.109 No.1
Manufacturing design of Korean sectors and ports for the ITER Vacuum Vessel (VV) has been developed to comply with the tight tolerance and severe inspection requirements. The first VV sector and lower ports are being fabricated slowly under strict regulations after verification using several real scale mock-ups and qualifications for welding, forming and NDE. During three years after start of fabrication, manufacturing progress on four poloidal segments of the first sector is that (1) all inner shells were welded, (2) forgings for complicate components have been machined, (3) port stubs and poloidal T-ribs were assembled, and (4) machined components are welded on the inner shells by narrow-gap TIG welding and electron beam welding. The progress of lower ports is that (1) inner shells of stub extensions were bent and treated with heat, (2) T-ribs were fabricated and examined by qualified phased array UT, (3) supporting pads and gussets have been machined, and (4) inner shells are assembled with T-ribs and machined forgings. The progress rate of manufacturing is around 40% up to the end of 2015 for the first sector and lower port stub extensions.
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