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[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering最新文献

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JT-60 operation results after its modification for higher plasma current with single null open divertor JT-60单空开导流器改造后的运行结果
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218923
I. Kondo, H. Horiike, Y. Neyatani, M. Matsukawa, T. Ando, R. Yoshino, T. Arai, H. Ninomiya, M. Yamamoto, T. Koike, K. Kodama, K. Miyachi, M. Honda, H. Hiratsuka
{"title":"JT-60 operation results after its modification for higher plasma current with single null open divertor","authors":"I. Kondo, H. Horiike, Y. Neyatani, M. Matsukawa, T. Ando, R. Yoshino, T. Arai, H. Ninomiya, M. Yamamoto, T. Koike, K. Kodama, K. Miyachi, M. Honda, H. Hiratsuka","doi":"10.1109/FUSION.1991.218923","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218923","url":null,"abstract":"The hardware performance of the JT-60U (JAERI Tokamak-60 Upgrade) tokamak machine was investigated in several aspects. The experimental operation has advanced to record D-D fusion power as high as 17 kW. The displacement of the toroidal field coil was measured, and the effect of reinforcement was confirmed. The dynamic displacement of the vessel was found to be a vibration with amplitude within 0.3 mm and relatively slow dumping. Regarding the first wall, the divertor suffered from the heat flow with the width of 4 to 5 cm that was close to the design value. The divertor armor was found to rise 500 degrees C at most for the neutral-beam heating of 20 MW for 2 s, and it is still operated with nitrogen gas circulation cooling. The power flow to the divertor is low due to large radiations of the main and divertor plasmas, while the purity of plasma was largely improved by introduction of glow discharge cleaning of 300 V*1 A.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"32 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124999509","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}
引用次数: 2
Experimental high heat load surface damage of graphite and refractory materials 高热负荷对石墨和耐火材料表面损伤的实验研究
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218799
M. Bourham, O. Hankins, W. Eddy, J. Hurley, J. Earnhart, J. Gilligan
{"title":"Experimental high heat load surface damage of graphite and refractory materials","authors":"M. Bourham, O. Hankins, W. Eddy, J. Hurley, J. Earnhart, J. Gilligan","doi":"10.1109/FUSION.1991.218799","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218799","url":null,"abstract":"Different grades of graphite and refractory material surfaces were exposed to pulsed high heat fluxes between 2 and 60 GW/m/sup 2/. Graphite ablation is reduced by 80 to 95% as a result of the self-protecting nature of the vapor shielding mechanism. Such ablation reduction helps in extending the lifetimes of plasma-facing components for large tokamak designs. The ablation of graphite is approximately the same for both transverse and normal exposure to the incident heat flux. Refractory materials erode at lower rates compared to other metallic surfaces. Molybdenum (sintered or arc cast) has lower erosion rate than titanium. Titanium erosion tends to saturate for incident heat fluxes above 10 GW/m/sup 2/, where the melt-shield is dominant. Cracks are absent from exposed titanium, which may suggest that the internal stresses due to thermal shocks do not exceed the modulus of rigidity. Tungsten has approximately no erosion for incident heat fluxes below 20 GW/m, but surface cracking may occur.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"34 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124561083","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}
引用次数: 1
Design of ICRF antennas for TFTR TFTR中ICRF天线的设计
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218939
S. Raftopoulos, R. Scillia, P. Bonanos, J. Hosea, J. Wilson, W. Enoch
{"title":"Design of ICRF antennas for TFTR","authors":"S. Raftopoulos, R. Scillia, P. Bonanos, J. Hosea, J. Wilson, W. Enoch","doi":"10.1109/FUSION.1991.218939","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218939","url":null,"abstract":"Two 4-MW ICRF (ion cyclotron range of frequencies) antennas have been designed for the Tokamak Fusion Test Reactor (TFTR). The antennas will be installed adjacent to the two existing antennas, bringing the maximum ICRF heating capacity to 12.5 MW. The design goals were to increase the loading to the plasma, to reduce the tendency for arcing, and to simplify the fabrication and assembly of the device. The antenna, consisting of an RF cavity with slots at the front end (facing the plasma), utilizes a center-mounted spline drive mechanism for positioning the device with respect to the plasma edge and for resisting the forces generated during disruptions. The Faraday shields are unique for each launcher, though they share common design elements. Both launchers use solid Inconel rods that are bent to a radius matching the plasma and tilted six degrees in order to be parallel with the combined poloidal and toroidal fields of the tokamak. The 'Bay K' launcher uses a single row shield while the 'Bay N' launcher incorporates a double row shield. Faraday shield protection and the center-grounded current straps are also discussed.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128957258","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}
引用次数: 1
Development of a man/machine interface system for the JT-60 upgrade 开发用于JT-60升级的人机接口系统
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218727
I. Yonekawa, M. Shimono, T. Totsuka, K. Yamagishi
{"title":"Development of a man/machine interface system for the JT-60 upgrade","authors":"I. Yonekawa, M. Shimono, T. Totsuka, K. Yamagishi","doi":"10.1109/FUSION.1991.218727","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218727","url":null,"abstract":"The authors describe the design and initial operation of a new JT-60 (JAERI Tokamak-60) man-machine interface system built in workstations. Development of the system was stimulated by the requirements of making of JT-60 operator interface more friendly on the basis of the past five years of operational experience. Eleven Sun/3 workstations and their supervisory minicomputer HIDIC V90/45 are connected through the standard network, Ethernet. The network is also connected to the existing ZENKEI minicomputer system through the shared memory on the HIDIC V90/45 minicomputer. Improved software, such as automatic setting of the discharge conditions, consistency check among the related parameters, and easy operation for discharge result data display, provides the user-friendly environments. This man-machine interface system leads to the efficient JT-60 upgrade operation.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129677196","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}
引用次数: 3
Compact ignition experiments: design and performance 小型点火实验:设计与性能
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218791
A. Angelini, B. Coppi, M. Nassi
{"title":"Compact ignition experiments: design and performance","authors":"A. Angelini, B. Coppi, M. Nassi","doi":"10.1109/FUSION.1991.218791","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218791","url":null,"abstract":"Compact high field experiments are shown to be suitable for producing low-temperature ignition (T/sub 0/ approximately=11 keV) of D-T plasma mixtures with n/sub 0/ approximately=10/sup 21/ m/sup -3/ under known criteria of both energetics and stability. The 12 MA plasma current considered for the Ignitor configuration is gradually induced in the plasma column while its cross section is increased, allowing the control of the current density distribution in such a way that the region where q<or=1 has a relatively small volume. This is done in order to avoid the onset of internal sawtooth oscillations that can prevent attaining ignition. The ohmic heating is maintained at relatively high levels up to ignition conditions, as the loop voltage retains a significant variation over the plasma radius. Since ignition can be attained by ohmic heating alone, injected heating systems in compact high field experiments should have the role of backups and be available, if needed, to suppress the possible onset of sawtooth oscillations, to control the temperature and the current density profiles, and to accelerate the attainment of ignition.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129850856","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}
引用次数: 0
Overview of TEXT control system upgrade TEXT控制系统升级概述
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218732
W. W. Mixon, D. Terry, D. Patterson, J. Dibble
{"title":"Overview of TEXT control system upgrade","authors":"W. W. Mixon, D. Terry, D. Patterson, J. Dibble","doi":"10.1109/FUSION.1991.218732","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218732","url":null,"abstract":"The upgrade to the Texas Experimental Tokamak, (TEXT) includes two new motor-generator sets, new vertical-field and divertor power supplies, and a new 500-kW ECH (electron cyclotron heating) gyrotron and its power supplies. Much of the monitoring and control of this hardware are done by a network of UNIX workstations running TACL control software. Additional capabilities needed during actual pulses, such as fast data-logging and the generation of waveforms and fast timing sequences, is provided by CAMAC modules controlled by VAX computers and X Windows terminals. These new systems are integrated with the old TEXT control and data-acquisition systems.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"35 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"131073239","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}
引用次数: 2
Monte-Carlo studies of radiation damage by fusion neutron in the first wall 第一壁核聚变中子辐射损伤的蒙特卡罗研究
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218688
X. Gao, Y. Hou, Z. Pan, Q.Y. Shao, J.X. Chen, S.M. Wu
{"title":"Monte-Carlo studies of radiation damage by fusion neutron in the first wall","authors":"X. Gao, Y. Hou, Z. Pan, Q.Y. Shao, J.X. Chen, S.M. Wu","doi":"10.1109/FUSION.1991.218688","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218688","url":null,"abstract":"A Monte Carlo Neutron Transport Program, NTGM, and Neutron Radiation Damage Program, NRDGM, are presented for studying radiation damage of the first wall. The programs are applied to a static multicomponent amorphous target. With the average wall load of 1 MW/m/sup 2/ the PKA (primary knock on atom) energy spectra (30 eV to 1 MeV), average displacement per atom rate (16.8 dpa/a), average helium and hydrogen production rates (204 appm/a and 623 appm/a) have been calculated for the first wall (type 316 stainless steel) using designed neutron spectra at the EHR (Experimental Hybrid Reactor) first wall. It is shown that the EHR's radiation damage is more serious than that of a pure fusion reactor.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"7 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130318486","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}
引用次数: 0
Variable-speed constant-frequency AC generator with flywheel for power supply system of the fusion facility 核聚变设施供电系统用飞轮变速恒频交流发电机
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218864
H. Chikaraishi, H. Kihara, R. Shimada
{"title":"Variable-speed constant-frequency AC generator with flywheel for power supply system of the fusion facility","authors":"H. Chikaraishi, H. Kihara, R. Shimada","doi":"10.1109/FUSION.1991.218864","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218864","url":null,"abstract":"An AC-excited variable speed generator with flywheel is proposed as a power supply for a nuclear fusion experimental facility. In this generator, the flywheel, whose speed varies depending on energy charging/discharging, is connected to a power line operated at a certain fixed frequency by means of a synchronous motor generator that is excited by a variable frequency converter, realizing energy charging and discharging. The advantages offered compared to a conventional generator are discussed in detail. It was shown through simulation that it is possible to connect a power load featuring a large time fluctuation without causing oscillation in the system if this flywheel is connected to the receiving point and power is charged or discharged by matching the fluctuation of load power in accordance with the frequency or voltage control of the utility power system.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130358409","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}
引用次数: 1
Study of plasma disruptions in JET and its implications on engineering requirements JET中等离子体干扰的研究及其对工程需求的影响
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218917
A. Tanga, M. Garribba, M. Hugon, M. Johnson, C. Lowry, C. Nardone, P. Noll, M. Pick, S. Saibene, G. Sannazzaro
{"title":"Study of plasma disruptions in JET and its implications on engineering requirements","authors":"A. Tanga, M. Garribba, M. Hugon, M. Johnson, C. Lowry, C. Nardone, P. Noll, M. Pick, S. Saibene, G. Sannazzaro","doi":"10.1109/FUSION.1991.218917","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218917","url":null,"abstract":"The authors discuss the problems associated with the decay of the plasma current in JET (Joint European Torus) disruptions. It is noted that the slow mode of plasma current decay may offer the best chances of minimizing the forces in high current disruptions. However, the plasma position needs to be controlled during the decay of the plasma current. The radial field position can be controlled by a sufficiently fast vertical field amplifier. For the control of the vertical position the two problems to be solved are the magnetohydrodynamic perturbations of the magnetic signals and the increased vertical destabilization, which coincides in time with the measured energy quench. It has been demonstrated that a substantial reduction of the vessel forces can be achieved by reducing plasma elongation prior to the disruption.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"49 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130037028","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}
引用次数: 2
Development and design of railgun system to pellet injector 弹丸喷射器轨道炮系统的开发与设计
[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI: 10.1109/FUSION.1991.218743
Y. Oda, M. Onozuka, S. Tsujimura, S. Kuribayashi, K. Shimizu, A. Sawaoka, H. Tamura
{"title":"Development and design of railgun system to pellet injector","authors":"Y. Oda, M. Onozuka, S. Tsujimura, S. Kuribayashi, K. Shimizu, A. Sawaoka, H. Tamura","doi":"10.1109/FUSION.1991.218743","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218743","url":null,"abstract":"Railgun systems for the application of pellet injectors have been investigated and developed in the experimental stage. One of the main features of these railgun systems is the use of a pulse laser beam to induce the initial plasma armature between rails to be accelerated. This unique feature provides a reduction of the supplied voltage to the breakdown between the rails in order to avoid any unnecessary breakdown between the rails and to reduce the erosion of the rails. The authors present results of experimental and theoretical research and introduce the design study for a repetitive pellet injection systems with an electromagnetic railgun based on the research progress.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"48 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130986812","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}
引用次数: 1
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