2011 IEEE/NPSS 24th Symposium on Fusion Engineering最新文献

{"title":"Thermal-hydraulic simulation of 80 kA safety discharge in the ITER Toroidal Field Model Coil (TFMC) using the 4C code","authors":"L. Savoldi Richard, R. Bonifetto, R. Zanino, R. Heller","doi":"10.1109/SOFE.2011.6052297","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052297","url":null,"abstract":"The Toroidal Field Model Coil (TFMC) was extensively tested in 2001–2002, up to maximum transport current of 80 kA and peak field of ∼ 10 T, in the TOSKA facility at the Karlsruhe Institute of Technology, Germany. Here we apply the 4C code, which was developed for the analysis of thermal-hydraulic transients in superconducting magnets, including winding, structures and cryogenic circuit, to the analysis of the TFMC safety discharge from 80 kA. The code is able to reproduce the main experimental features, within the limitations due to no more fully available information about the details of the cryogenic circuit, which play here a much more important role than at lower currents.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"206 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123092825","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Limiter-Coil Current Controller for Flux-Coil Generated FRC","authors":"M. Slepchenkov, M. Morehouse, V. Kiyashko, F. Wessel, N. Rostoker, N. Bolte, T. Roche","doi":"10.1109/SOFE.2011.6052327","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052327","url":null,"abstract":"This paper describes the Limiter-Coil Current Controller for the Flux-Coil Generated Field-Reversed Configuration plasma confinement device. It provides independent current regulation for each pair of limiter-coils, allowing control of the magnetic field profile along the horizontal axis of the chamber. A power circuit description and the main principles of the control system design and operation of the proposed Current Controller are presented. The experimental results demonstrate that controllability of radial position as well as positioning the plasma in the center of device has been achieved by using the developed system.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124228544","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Design feasibility analysis of the robot for EAST tokamak flexible in-vessel inspection","authors":"X. Peng, Y. Song, Y. Yang, P. Qiao, X. Ji","doi":"10.1109/SOFE.2011.6052217","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052217","url":null,"abstract":"EAST is a full superconducting tokamak fusion experiment device with ‘D’ shape vacuum vessel and toroidal coils and actively cooled plasma facing components (PFCs), which aims at studying the scientific and engineering issues under steady state operation. It is difficult but very important to know well the operating state of the components in the vacuum vessel during plasma operation campaign for the help of guiding operation plan and understanding physical phenomena. A robotic system (called flexible in-vessel inspection robot, FIVIR) is proposed to inspect the surface of plasma facing components to know the performance of first wall, such as erosion and desquamation. Because of the geometric requirement and the intensity of ports usage arrangement, two FIVIRs are planned installing toroidal symmetry on EAST. Each FIVIR is a series-wound robot with ten degrees of freedom consisting of main robot and end-effector. The main robot has the primary function that transports the end-effector and associated process tools into the vacuum chamber in the equatorial plane at R=1.94m and back to the storage port, which has the benefit that easy control of the FIVIR and easy position calculation of the end-effector. All the joints in the FIVR are driven by actuators. The workspace of the robot is analyzed to see whether it can reach any point of the plasma facing surface in the distance of 15mm and the range of ±90°along toroidal direction.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"46 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126417628","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"A proposed scraper element to protect the end of the W7-X divertor target elements","authors":"A. Peacock, J. Kisslinger, J. Boscary, J. Geiger, F. Hurd, R. Konig, M. Krychowiak, R. Stadler, M. Smirnow, J. Tretter, A. Werner","doi":"10.1109/SOFE.2011.6052300","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052300","url":null,"abstract":"The three main areas of the W7-X divertor target are: the horizontal target, the vertical target and the high iota tail, with a pumping gap between the horizontal and vertical targets. For each of the standard operational scenarios the target has been designed so that, based on vacuum field calculations, the plasma strike points lie away from the ends of the target. Each target consists of CFC armoured water cooled poloidally running target elements capable of operating reliably in these central regions at up to 10MW/m2 in steady state operation, as necessary for the standard configurations. Due to the U-turn shape of the cooling channel at the pumping gap end of the elements the cooling is not optimal and a reduced performance is expected. However, recent studies of experiment scenarios, also now taking into account the influence of bootstrap currents, showed that the strike point drifts over the ends of the target elements adjacent to the pumping gap on the L/R time scale; potentially leading to damage of the elements in these scenarios. Various operational methods have been studied to satisfactorily avoid this situation without success. The paper describes design changes being made to improve the ability of the end of the elements to accept reasonable power levels, however it is not expected that the elements in these regions will meet the full power requirements. Hence, this paper also describes the design of a protection element; the purpose of this so-called “scraper element” is to intercept the power to the targets before the full power reaches the sensitive end of the elements. This is done without reducing significantly the pumping at the pumping gap and addresses issues such as how to control local impurity flows. The programme of work concerning design and technology qualification still needed to realise this scraper element is described.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"20 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129894422","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Low loss and compact power supply for superconducting magnet using MERS soft-switching converter","authors":"T. Isobe, K. Ito, T. Matsukawa, R. Shimada","doi":"10.1109/SOFE.2011.6052230","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052230","url":null,"abstract":"This paper proposes a new circuit configuration for bi-directional magnet power supply. The proposed power supply can handle bi-directional power flow; therefore, can be applied to superconducting magnet, which is usually required to discharge stored energy. The proposed converter is characterized by soft-switching operation and eliminated smoothing capacitor. These features make construction of a large scale magnet power supply easy by using semi-conductor devices without reverse voltage block capability, which are well used in industries. Operation and control principle of this converter, and some experimental results with a small scale model are also described.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"109 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124056490","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Differences into HT and HTO concentrations in air into the Western Mediterranean Basin and Continental Europe and safety related issues","authors":"P. Castro, M. Velarde, J. Ardao, J. Perlado, L. Sedano","doi":"10.1109/SOFE.2011.6052268","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052268","url":null,"abstract":"Real time Tritium concentrations in air in two chemical forms, HT and HTO, coming from an ITER-like fusion reactor as source were coupled the European Centre Medium Range Weather Forecast (ECMWF) numerical model with the Lagrangian Atmospheric-particle dispersion model FLEXPART. This tool was analyzed in nominal tritium discharge operational reference and selected incidental conditions affecting the Western Mediterranean Basin during 45 days during summer 2010 together with surface “wind observations” or weather data based in real hourly observations of wind direction and velocity providing a real approximation of the tritium behavior after the release to the atmosphere from a fusion reactor. From comparison with NORMTRI - a code using climatologically sequences as input - over the same area, the real time results have demonstrated an apparent overestimation of the corresponding climatologically sequence of Tritium concentrations in air outputs, at several distances from the reactor. For this purpose two development patterns were established. The first one was following a cyclonic circulation over the Mediterranean Sea and the second one was based on the plume delivered over the Interior of the Iberian Peninsula and Continental Europe by another stabilized circulation corresponding to a High Pressure System. One of the important remaining activities defined then, was the qualification tool. In order to validate the model of ECMWF/FLEXPART we have developed of a new complete data base of tritium concentrations for the months from November 2010 to March 2011 and defined a new set of four patterns of HT transport in air, in each case using real boundary conditions: stationary to the North, stationary to the South, fast and very fast displacement. Finally the differences corresponding to those four early patterns (each one in assessments 1 and 2) has been analyzed in terms of the tuning of safety related issues and taking into account the primary phase of tritium modeling, from its discharge to the atmosphere to the deposition on the ground, will affect to the complete tritium environmental pathway altering the chronic dose by absorption, reemission and ingestion both from elemental tritium, HT and from the oxide of tritium, HTO.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"41 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126784020","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Analysis of harmonic current suppression and reactive power compensation on 125MVA motor generator","authors":"Wang Yingqiao, Yao Lie-ying, Peng Jianfei","doi":"10.1109/SOFE.2011.6052339","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052339","url":null,"abstract":"The load of 125MVA motor generator on HL-2A is introduced. The frequency of harmonics on the output current is analyzed and it is verified by Fourier decomposition to measured signal. The harmonic current and reactive current on power line of generator are calculated from its phase voltages and currents. The simulation results are helpful for the study of active power filter for 125MVA generator.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"5 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127814504","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Preliminary test and evaluation of non-destructive examination for ITER First Wall development in Korea","authors":"Suk-Kwon Kim, E. Lee, J. Yoon, H. Jung, Dong Won Lee, Byoung-Yoon Kim","doi":"10.1109/SOFE.2011.6052288","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052288","url":null,"abstract":"ITER First Wall (FW) includes beryllium armour joined to a Cu heat sink with a stainless steel back plate. These first wall panels are one of the critical components in the ITER tokamak with a maximum surface heat flux of 5 MW/m2. So, a qualification test needs to be performed with the goal to qualify the joining technologies required for the ITER first wall. Various mockups were fabricated to develop the manufacturing procedure of first wall components. For the non-destructive examination (NDE) of the fabricated mockups, an ultrasonic test (UT) was performed with optimized probes. The UT test was performed by using a three-axis digital ultrasonic C-scan system and software. The system is comprised of an ultrasonic pulser/receiver, model Panametrics 5800PR, a personal computer having an internal analog/digital converter board and four axis motion control board, and a three-axis scanning tank. Two type transducers were used for this experiment. One was Panametrics V312-SU, having a center frequency of 10 MHz (nominal), a piezoelectric element diameter of 0.25 inch with a flat protective layer for the Be/Cu. The other was Panametrics V309-SU with a center frequency of 5 MHz and an element diameter of 0.5 inch for the Cu/SS interface. Winspect software controlled all aspects of data acquisition, motion control, data archiving, and image display. Based on the acceptance criteria, average amplitude of the interface signals, which have about 50% of the reference echo amplitude, was recorded and analyzed on each beryllium tile. Image analysis software analyzed the statistics of amplitude distribution and calculated the unacceptable area. Each mockup that passed these UT tests was concluded to qualify the joining technologies required for an ITER first wall by using high heat flux test facility. As a result of these qualification tests based on the acceptance criteria of an ITER first wall, the fabrication technologies will be utilized to develop the first wall of plasma facing components.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"48 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"114922978","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Simulation of thermal-hydraulic transients in the KSTAR PF1 coil using the 4C code","authors":"R. Zanino, A. Kholia, L. Richard, Y. Chu, S. Park, H. J. Lee","doi":"10.1109/SOFE.2011.6052291","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052291","url":null,"abstract":"KSTAR is a fully superconducting tokamak, in operation since 2008 at the National Fusion Research Institute in Korea. All coils are wound using cable-in-conduit conductors and cooled with forced-flow supercritical helium (SHe) at 4.5 K and 5.5 bar. We consider here the central pair, PF1U/L, of the central solenoid coils; during operation these coils are subjected to sharp current transients, which induce AC losses in the coil. The thermal hydraulic transient following a trapezoidal current pulse, with ramp up to 10 kA at a rate of 1 kA/s and ramp down to 0 kA at a rate of 10 kA/s, is simulated here using the 4C code, and the results are compared with the measurements.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"130 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116806695","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Calculation of stray magnetic field effects on the operation of the ITER electron cyclotron system","authors":"F. Li, S. Alberti, J. Hogge, I. Pagonakis","doi":"10.1109/SOFE.2011.6052289","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052289","url":null,"abstract":"In a multi-gyrotron system such as the one presently designed for the ITER ECH & ECCD system, stray magnetic fields can significantly alter the operational capabilities of the global system. A numerical study was carried out within the European Gyrotron Consortium (EGYC) to assess the importance of the different effects and their impact on the gyrotron operation.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"7 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2011-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128117227","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}