S. Peruzzo, P. Bettini, N. Marconato, A. Soppelsa, R. Albanese, M. Caputano, M. Mattei, G. Rubinacci, F. Villone
{"title":"Integrated procedure for halo current reconstruction in ITER","authors":"S. Peruzzo, P. Bettini, N. Marconato, A. Soppelsa, R. Albanese, M. Caputano, M. Mattei, G. Rubinacci, F. Villone","doi":"10.1109/SOFE.2011.6052248","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052248","url":null,"abstract":"The paper describes an integrated procedure for the reconstruction of halo currents expected in ITER. The procedure is based on simulation and reconstruction codes, partially adapted from existing codes and partly developed specifically for this purpose. The ultimate goal of this integrated procedure is the assessment of the performance and the possible optimization of the halo current diagnostic system foreseen in ITER. The preliminary results indicate that an alternative distribution of the present layout of halo current sensors could improve the reconstruction capability of this diagnostic system.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"51 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":"133511223","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}
S. Ramakrishnan, C. Neumeyer, J. Lawson, R. Mozulay, E. Baker, R. Hatcher, N. Desai, W. Que, Xin Zhao
{"title":"Power system for NSTX upgrade","authors":"S. Ramakrishnan, C. Neumeyer, J. Lawson, R. Mozulay, E. Baker, R. Hatcher, N. Desai, W. Que, Xin Zhao","doi":"10.1109/SOFE.2011.6052347","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052347","url":null,"abstract":"This The National Spherical Torus Experiment (NSTX) has been designed and installed in the existing facilities at Princeton Plasma Physic Laboratory (PPPL). Most of the hardware, plant facilities, auxiliary sub-systems, and power systems originally used for the Tokamak Fusion Test Reactor (TFTR) have been used with suitable modifications to reflect NSTX needs. At present, the NSTX power system is feeding thirteen (13) circuits from the Power converters. An upgrade of the NSTX center stack is proposed. This entails a much higher Toroidal Field Current from 71.2kA to 129.8kA, and requires major configuration changes including doubling the number of parallel strings of rectifiers along with associated power loop changes. Also, three additional coils will be installed in the machine. The control and protection of the rectifiers have to be replaced to reflect state of the art features to enhance the performance. This paper describes the details of the proposed Power system for NSTX upgrade.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"32 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":"114216916","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":"Improving the linearity of the AD8361 “Tru-Pwr” RF detector IC","authors":"N. Greenough","doi":"10.1109/SOFE.2011.6052265","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052265","url":null,"abstract":"The AD8361 is a wideband linear RMS radio-frequency (RF) detector IC widely used in the RF industry. This paper presents a method to extend the dynamic range of the detector to nearly 40 decibels, over a range from less than −30dBm to +8dBm with absolute accuracy typically +0.5/−1dB. In addition, most samples can be made to track to a very high degree over an even wider range. The increase in accuracy and tracking allows improved power calibration, real-time power regulation, and calculation of VSWR (voltage standing wave ratio) for the multimegawatt RF transmitters used to heat plasmas on NSTX at PPPL. The method presented here is simpler and lower cost than the dual-detector-amplifier technique presented by its manufacturer. Test results and distributions are presented for approximately 20 samples of a dual-detector module built by PPPL.","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":"130560842","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}
A. Panin, W. Biel, Y. Krasikov, O. Neubauer, D. Bardawil
{"title":"Structural analysis of a prototype fast shutter for ITER cCXRS diagnostic","authors":"A. Panin, W. Biel, Y. Krasikov, O. Neubauer, D. Bardawil","doi":"10.1109/SOFE.2011.6052250","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052250","url":null,"abstract":"Optical lifetime of the first mirror is a critical issue for the ITER upper port plug core charge exchange spectroscopy diagnostic (cCXRS). A fast shutter is engaged to protect the mirror from depositions between measurements. The prototype shutter will be examined in a test vacuum vessel that is now under development in the Forschungszentrum Jülich, Germany. Being located near the plasma, the shutter operates under severe thermal and electromagnetic (EM) loads. The multi-field analyses conducted for the shutter are presented in the paper. Since the fast shutter can operate within 1 second, its static structural analysis should be accompanied by dynamic studies. The paper pays attention to numerical strategy used for a multi-field ANSYS modeling of a complex structure. The shutter structural performance under the service, thermal and EM loading is in line with requirements. Solution for a problem of high local thermo-stresses revealed by the analysis is proposed. Problems connected with other possible port plug - shutter layouts are discussed.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"67 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":"124725334","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}
A. Drozdovskiy, A. Golubev, Yu.B. Novozhilov, P. Sasorov, S. Savin, V. Yanenko, V. Bochkov
{"title":"Plasma lens for transformation the ITEP heavy ion accelerator with TDI-pseudosparks","authors":"A. Drozdovskiy, A. Golubev, Yu.B. Novozhilov, P. Sasorov, S. Savin, V. Yanenko, V. Bochkov","doi":"10.1109/SOFE.2011.6052223","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052223","url":null,"abstract":"Transportation and focusing of intense heavy-ion beams is an important issue for heavy ion beam-driven inertial confinement fusion and physics of high energy densities. Application of plasma lens offers certain advantages over traditional systems based on quadruple lenses. A description of the plasma lens with high-power high-current (up to 400 kA) TDI-pseudosparks as switching elements and experimental results of preliminary studies of plasma lens designed for heavy ion accelerator-accumulated facility TWAC-ITEP are reported. It is shown that a focusing capability of plasma lens depends on a stage of plasma discharge development. In a particular stage it is possible to employ sharp focusing and compress the beam into a very small spot. In other stages when the magnet field is non-linear it is possible to shape various beam configurations, in particular, tube structures. In the report the results of investigations implemented with beams of C+6 and F+6 ions with energy of 200 MeV/a.e.m. are reported. The obtained results are analyzed.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"24 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":"127808651","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":"Coupled multiphysics analysis of the TF coil structure in the NSTX upgrade","authors":"A. Zolfaghari, T. Willard, M. Smith","doi":"10.1109/SOFE.2011.6052349","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052349","url":null,"abstract":"The National Spherical Torus Experiment (NSTX) is being upgraded to increase plasma current to 2 MA and central toroidal magnetic field to 1 Tesla [1]. The upgrades include a replacement of the centerstack and addition of a second neutral beam. The Inner legs of the TF coil which are at the core of the new larger NSTX upgrade center stack are designed to carry twice the current of the existing TF coils. The inner and outer legs of the TF coil are connected through a set of flexible straps that allow for the thermal growth of the center stack and the out of plane twisting moments in the TF coils. Electromagnetic interaction of the TF, OH and PF coils results in loads on the TF coil structure. The TF flexible straps and structural components of the machine have to withstand these loads. Coupled electromagnetic, thermal and structural analyses were performed. The results of these analyses, which will be presented in detail in this paper, have led to the validation of the design of TF flexible straps and compliance with the requirements of the NSTX structural design criteria.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"21 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":"129964822","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}
Z.C. Sun, P.Y. Lee, C. Pan, B. Hou, S. Han, Y. Pei, W. Long
{"title":"The development of argon arc brazing with Cu-based filler for ITER thermal anchor attachment","authors":"Z.C. Sun, P.Y. Lee, C. Pan, B. Hou, S. Han, Y. Pei, W. Long","doi":"10.1109/SOFE.2011.6052245","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052245","url":null,"abstract":"Thermal anchor is the key components of ITER magnet supports to maintain the low temperature for the normal operation of superconducting coils. During the advanced research of ITER thermal anchor attachment, dozens of brazing filler and several kinds of brazing technique have been developed and investigated. Argon arc brazing with Cu-based filler was chosen as the principal method for the attachment of thermal anchor. The brazing temperature of Cu-based filler is over 1000°C,but heat input is relatively low for shallower heating depth of argon arc brazing. Lower heat input is good for the control of brazing deformation. It is no need to clean after brazing because for argon arc brazing there is no brazing flux used. The test result shows that Cu-based alloy have the best mechanical properties at both room temperature and 77K for high brazing temperature. Detail of argon arc brazing with Cu-based filler have been investigated in this article.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"4 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":"129708570","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":"Absolute calibration of the NSTX neutron monitor system","authors":"A. Roquemore, D. Darrow, S. Medley","doi":"10.1109/SOFE.2011.6052263","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052263","url":null,"abstract":"NSTX has a complement of six neutron detectors consisting of two fission chambers, one NE-451 ZnS scintillator and 3 plastic BC-400 scintillators. The primary purpose of the fission chambers is to provide an absolute calibration of the neutron rate, while the scintillator detectors monitor fast excursion in the neutron yield due for instance, to fast MHD events. Within the last 10 years NSTX has performed 4 separate calibrations of the neutron monitoring system. Initially, a californium neutron source on a long tether was introduced into the vessel through 10 different top ports on NSTX corresponding to 10 of the 12 bays of the vessel. Each of the ports was at the same major radius just slightly larger than the nominal plasma major radius and a point-wise ring source was simulated to perform the calibration. Recently, the fission chambers were relocated to accommodate new equipment and the detector system required recalibration. This most recent calibration employed a commercial G-gauge model train and three different diameter circular tracks to transport the 252CF neutron source around the midplane of the NSTX vessel. In each of the calibrations, the fission chambers were operated in the pulse counting mode. During plasma operations one of the detectors transitions to the pulse saturated or current mode of operation. To complete the calibration, a series of low performance He discharges heated with one deuterium neutral beam were performed. Neutrons in this case come predominantly from beam-beam reactions. These low-yield discharges produced neutron levels that allowed the FC2 to remain in pulse counting mode while FC1 transitioned into the current mode. This allows a cross calibration to be performed between FC2 in pulse counting mode and FC1 in the current mode. The current mode value is then transferred to each of the four scintillating detectors. The results of the four insitu calibrations are presented.","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":"126590386","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":"The simulation and numerical analysis for ITER first PF(poloidal field coil) feeder","authors":"S. Liu, Y. Song, K. Lu, Z. Wang","doi":"10.1109/SOFE.2011.6052309","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052309","url":null,"abstract":"The ITER feeder systems connect the ITER magnet systems located inside the main cryostat to the cryo-plant, power-supply and control system interfaces outside the cryostat. The main purpose of the feeders is to convey the cryogenic supply and electrical power to the coils as well as house the instrumentation wiring. The Feeder carries superconducting busbars, supercritical cryo-pipes and instrumental pipes from the CTB to the coil. The PF busbar which carries 52kA current will suffer from high Lorentz force due to the background magnetic field inspired by the coils and the self field between every pair of busbars. Peak magnetic force could be 6tons/m in the ICF region that requires dense supports. But to minimize the heat load to the busbars as well as the cryo-pipes, fewer and weaker supports design is proposed, so a balance between mechanical strength and thermal insulation performance should be achieved. This paper presents the simulation and analysis on support system design for ITER 1st PF feeder including the S-Bend Box (SBB), the Cryostat Feed-through (CFT), the In-Cryostat-Feeder (ICF), especially for a pair of busbars and main cooling-pipes firstly. This analysis aims to get real magnetic force load under the worst scenario, an electric-magnetic coupled analysis which includes the busbars and the coils is performed, then the Lorentz force result is imported into the mechanical analysis, applied on the busbars, meanwhile the supports and the containment duct are contained in the finite element model (FEM) to check the full system performance under Lorentz forces, earth gravity and thermal contract at 4.5K. Based on the simulative and analytical results, the quantity and the spaces between supports in the 1st PF feeder have been studied and the detail design optimized.","PeriodicalId":393592,"journal":{"name":"2011 IEEE/NPSS 24th Symposium on Fusion Engineering","volume":"115 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":"127614471","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}
H. Yang, J. Bak, K. Kim, Y. Oh, Y.S. Kim, B.C. Kim, Y.M. Park, W. Kim, K.R. Park, J. Sa, H. Kim, K. Cho, M. Park, K.H. Kim, T. Ha, K. Park, H. Hong, M. Kwon, G.S. Lee, C. Choi, N. Her, K. Im, B.S. Im, H. S. Jang
{"title":"The construction of ITER, viewed from lessons learned from the KSTAR project","authors":"H. Yang, J. Bak, K. Kim, Y. Oh, Y.S. Kim, B.C. Kim, Y.M. Park, W. Kim, K.R. Park, J. Sa, H. Kim, K. Cho, M. Park, K.H. Kim, T. Ha, K. Park, H. Hong, M. Kwon, G.S. Lee, C. Choi, N. Her, K. Im, B.S. Im, H. S. Jang","doi":"10.1109/SOFE.2011.6052225","DOIUrl":"https://doi.org/10.1109/SOFE.2011.6052225","url":null,"abstract":"The construction of ITER is an extremely important project, not only within the fusion society but also for mankind: By solving critical energy and environmental problems, another major step in human history will be taken. Design, construction, and assembly of an ultra large scale machine such as ITER require thoroughly well defined plans, strategies, and predictions of potential problems and solutions. It is believed that preceding devices and projects may provide useful references for the several important considerations noted above. The KSTAR (Korea Superconducting Tokamak Advanced Research), a representative superconducting tokamak, has the most similar characteristics to the design concept of the ITER. Therefore, the lessons learned from KSTAR can be categorized according to the following engineering aspects: 1) policies to prioritize decisions, 2) catch-up plans for delayed schedules, 3) strategies in site assembly, 4) troubleshooting, 5) standard indexes or guides for tests and acceptance of individual systems and of site assemblies, and 6) interfaces that can be easily omitted in view of the system integration. This paper will summarize the lessons we have learned from the KSTAR project, focusing on engineering related points that can be considered to suggest guidelines for the ITER construction.","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":"122621828","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}