Pub Date : 1991-09-30DOI: 10.1109/FUSION.1991.218709
F. McClintock, J. Feng, R. Vieira
An uncertainty analysis combines the resulting prediction limits with estimated effects of a number of factors, of which the most important are: the statistical variability and limited number of specimens, the largest undetected crack length, the plate-to-plate variability, and the allowance for oversights. The total effect of these (and many more minor) effects is to reduce the allowable stress, for chosen odds against fracture of 10000 to 1, to about 2/3 of the central statistical value. The analysis highlights the factors needing further study and illustrates the value of statistical and uncertainty analyses, which should be combined with cost-benefit and fault-free analyses to complement code-based design.<>
{"title":"Using statistical and uncertainty analyses in design, applied to a tokamak central solenoid","authors":"F. McClintock, J. Feng, R. Vieira","doi":"10.1109/FUSION.1991.218709","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218709","url":null,"abstract":"An uncertainty analysis combines the resulting prediction limits with estimated effects of a number of factors, of which the most important are: the statistical variability and limited number of specimens, the largest undetected crack length, the plate-to-plate variability, and the allowance for oversights. The total effect of these (and many more minor) effects is to reduce the allowable stress, for chosen odds against fracture of 10000 to 1, to about 2/3 of the central statistical value. The analysis highlights the factors needing further study and illustrates the value of statistical and uncertainty analyses, which should be combined with cost-benefit and fault-free analyses to complement code-based design.<<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":"115541164","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}
Pub Date : 1991-09-30DOI: 10.1109/FUSION.1991.218766
R. Peterson, R. Englestad, G. Kulcinski, E. Lovell, J. Macfarlane, E. Mogahed, G. Moses, S. Rutledge, M. Sawan, I. Sviatoslavsky, G. Sviatoslavsky, L. Wittenberg
LIBRA-LiTE is a conceptual design for a 1300-MWe power plant using light ion inertial fusion. LIBRA-LiTE differs from the LIBRA design in its use of ballistically focused light ions to drive the target. Focusing magnets are positioned 2.05 m from the target, which, to mitigate neutron damage effects, has required a novel magnet design using liquid lithium as a conductor. A sacrificial film of liquid lithium protects the magnets, the target chamber side walls and bottom from the X-rays and debris released by the target microexplosion. The target neutrons deposit in a tritrium breeding blanket of liquid lithium confined to woven metal tubes on the sides and in a pool on the bottom. The top of the target chamber is a metallic dome removed far enough (16 m) from the target to be a lifetime component.<>
{"title":"LIBRA-LiTE, a light ion inertial confinement fusion reactor with ballistic ion propagation","authors":"R. Peterson, R. Englestad, G. Kulcinski, E. Lovell, J. Macfarlane, E. Mogahed, G. Moses, S. Rutledge, M. Sawan, I. Sviatoslavsky, G. Sviatoslavsky, L. Wittenberg","doi":"10.1109/FUSION.1991.218766","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218766","url":null,"abstract":"LIBRA-LiTE is a conceptual design for a 1300-MWe power plant using light ion inertial fusion. LIBRA-LiTE differs from the LIBRA design in its use of ballistically focused light ions to drive the target. Focusing magnets are positioned 2.05 m from the target, which, to mitigate neutron damage effects, has required a novel magnet design using liquid lithium as a conductor. A sacrificial film of liquid lithium protects the magnets, the target chamber side walls and bottom from the X-rays and debris released by the target microexplosion. The target neutrons deposit in a tritrium breeding blanket of liquid lithium confined to woven metal tubes on the sides and in a pool on the bottom. The top of the target chamber is a metallic dome removed far enough (16 m) from the target to be a lifetime component.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"355 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":"115168777","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}
Pub Date : 1991-09-30DOI: 10.1109/FUSION.1991.218880
P. Heitzenroeder
The toroidal field coil system of the Burning Plasma Experiment (BPX) consists of 18 beryllium copper magnets arrayed in a wedged configuration with a major radius of 2.6 m and a field strength capability on axis of 9.0 T. The toroidal array is constructed from six 3-coil modules to facilitate remote recovery in the event of a magnet failure after nuclear activation precludes hands-on servicing. The magnets are of a modified Bitter plate design with partial cases of type 316-LN stainless steel welded with Inconel 182 weld wire. The coil turn plates are fabricated from CDA C17510 beryllium copper with optimized mechanical, thermal, and electrical characteristics. Cryogenic cooling is used to reduce power dissipation and to enhance performance. The magnets are cooled between experimental pulses by pressurized liquid nitrogen flowing through channels in the edges of the coil turns, allowing one full-power pulse per hour. Overturning forces are reacted by friction forces generated by the wedging pressure in the central leg regions and by case and structure in the other regions of the coil. The magnets are designed to structural design criteria modeled after the ASME Boiler and Pressure Vessel Code, Section III, but with appropriate changes.<>
{"title":"BPX toroidal field coil design","authors":"P. Heitzenroeder","doi":"10.1109/FUSION.1991.218880","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218880","url":null,"abstract":"The toroidal field coil system of the Burning Plasma Experiment (BPX) consists of 18 beryllium copper magnets arrayed in a wedged configuration with a major radius of 2.6 m and a field strength capability on axis of 9.0 T. The toroidal array is constructed from six 3-coil modules to facilitate remote recovery in the event of a magnet failure after nuclear activation precludes hands-on servicing. The magnets are of a modified Bitter plate design with partial cases of type 316-LN stainless steel welded with Inconel 182 weld wire. The coil turn plates are fabricated from CDA C17510 beryllium copper with optimized mechanical, thermal, and electrical characteristics. Cryogenic cooling is used to reduce power dissipation and to enhance performance. The magnets are cooled between experimental pulses by pressurized liquid nitrogen flowing through channels in the edges of the coil turns, allowing one full-power pulse per hour. Overturning forces are reacted by friction forces generated by the wedging pressure in the central leg regions and by case and structure in the other regions of the coil. The magnets are designed to structural design criteria modeled after the ASME Boiler and Pressure Vessel Code, Section III, but with appropriate changes.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"30 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":"123053524","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}
Pub Date : 1991-09-30DOI: 10.1109/FUSION.1991.218717
D. Petersen
A new timing system has been designed to meet the requirements for the one megawatt test set (MWTS). This test set is a system of power supplies, support systems, controls, and monitors that will be used for the development of 1-MW gyrotrons. The purpose of the timing system is to provide timing signals for control of the gyrotron's cathode, anode, and heater power supplies as well as oscilloscope, digitizer, and other control or diagnostic triggers. Some unique timing requirements include four main operating modes: single pulse, repetitive pulse, continuous wave (CW), and CW cathode with repetitively pulsed anode. Timing adjustments can be made while the tube is running with no adverse effects. This modular, distributed timing system is implemented using two CAMAC modules: the master timing controller and the two channel timing generator. A single master timing controller provides real-time control and synchronization for all timing generators in the system. The timing generators provide triggers having adjustable delay and duration to the various system components.<>
{"title":"A modular timing system for megawatt gyrotrons","authors":"D. Petersen","doi":"10.1109/FUSION.1991.218717","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218717","url":null,"abstract":"A new timing system has been designed to meet the requirements for the one megawatt test set (MWTS). This test set is a system of power supplies, support systems, controls, and monitors that will be used for the development of 1-MW gyrotrons. The purpose of the timing system is to provide timing signals for control of the gyrotron's cathode, anode, and heater power supplies as well as oscilloscope, digitizer, and other control or diagnostic triggers. Some unique timing requirements include four main operating modes: single pulse, repetitive pulse, continuous wave (CW), and CW cathode with repetitively pulsed anode. Timing adjustments can be made while the tube is running with no adverse effects. This modular, distributed timing system is implemented using two CAMAC modules: the master timing controller and the two channel timing generator. A single master timing controller provides real-time control and synchronization for all timing generators in the system. The timing generators provide triggers having adjustable delay and duration to the various system components.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"339 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":"124770234","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}
Pub Date : 1991-09-30DOI: 10.1109/FUSION.1991.218698
K. Yoshikawa, Y. Yamamoto, H. Toku, S. Hashimoto, N. Komoda
A novel plasma neutralizer concept for a very simple structure is presented by making use of magnetron discharge for efficient plasma production with higher electron temperatures. Preliminary experimental results show electron temperatures as high as 20 eV, and 8*10/sup 11/ cm/sup -3/ electron density in an argon plasma, which are both promising for the plasma neutralizer. The effects of magnetic fields on the beam deflection are found negligible for extremely energetic beams like the 1.3-MeV D/sup -/ beams for ITER (International Thermonuclear Experimental Reactor). Issues for further improvements of plasma parameters are discussed.<>
{"title":"A plasma neutralizer by use of magnetron discharge","authors":"K. Yoshikawa, Y. Yamamoto, H. Toku, S. Hashimoto, N. Komoda","doi":"10.1109/FUSION.1991.218698","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218698","url":null,"abstract":"A novel plasma neutralizer concept for a very simple structure is presented by making use of magnetron discharge for efficient plasma production with higher electron temperatures. Preliminary experimental results show electron temperatures as high as 20 eV, and 8*10/sup 11/ cm/sup -3/ electron density in an argon plasma, which are both promising for the plasma neutralizer. The effects of magnetic fields on the beam deflection are found negligible for extremely energetic beams like the 1.3-MeV D/sup -/ beams for ITER (International Thermonuclear Experimental Reactor). Issues for further improvements of plasma parameters are discussed.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"19 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":"125032977","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}
Pub Date : 1991-09-30DOI: 10.1109/FUSION.1991.218794
R. Peterson, J. Macfarlane, P. Wang
The authors have investigated the target chamber designs for two IFE (inertial-confinement fusion energy) reactors (SOMBRERO and OSIRIS). The CONRAD computer code has been used to analyze certain critical aspects of these designs. Auto-neutralized transport is considered and a gas density is used that precludes protection of the first surface of the target chamber from X-rays and ions. The dominant issue in the design of the SOMBRERO laser fusion target chamber is the reradiation of absorbed target energy from the gas to the wall of the target chamber. In the OSIRIS heavy ion fusion target chamber, vaporization of material from the wall is the most important consideration. In SOMBRERO, 0.5 torr of xenon gas should allow beam transport and will protect the graphite wall vaporization by target energy. In OSIRIS, it was found that the FLIBE is vaporized and that a high peak pressure but moderate impulse shock reaches the vapor/liquid interface in the FLIBE.<>
{"title":"Target chamber gas response and vaporization in a laser and a heavy ion beam IFE reactor","authors":"R. Peterson, J. Macfarlane, P. Wang","doi":"10.1109/FUSION.1991.218794","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218794","url":null,"abstract":"The authors have investigated the target chamber designs for two IFE (inertial-confinement fusion energy) reactors (SOMBRERO and OSIRIS). The CONRAD computer code has been used to analyze certain critical aspects of these designs. Auto-neutralized transport is considered and a gas density is used that precludes protection of the first surface of the target chamber from X-rays and ions. The dominant issue in the design of the SOMBRERO laser fusion target chamber is the reradiation of absorbed target energy from the gas to the wall of the target chamber. In the OSIRIS heavy ion fusion target chamber, vaporization of material from the wall is the most important consideration. In SOMBRERO, 0.5 torr of xenon gas should allow beam transport and will protect the graphite wall vaporization by target energy. In OSIRIS, it was found that the FLIBE is vaporized and that a high peak pressure but moderate impulse shock reaches the vapor/liquid interface in the FLIBE.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"13 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":"124129561","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}
Pub Date : 1991-09-30DOI: 10.1109/FUSION.1991.218653
E. Frattolillo, S. Migliori, F. Mirizzi, F. Scaramuzzi
A diagnostic apparatus has been designed and tested, giving mass and speed measurements and in-flight pictures of the solid D/sub 2/ pellets for the high-speed (up to 3.3 km/s) single-pellet injector (SPIN) to be installed on the Frascati Tokamak Upgrade, (FTU), in order to completely characterize each of the launched pellets. A detailed description of the apparatus and of experimental results obtained with a prototype injector is given. From the point of view of speed determination, the system gives reliable results. Some problems have been detected on the volume (mass) determination, because the inner surfaces of the cavities have not been accurately treated for vacuum since they are prototypes. A new set of cavities is under construction and the whole setup will be improved according to what the experience with the prototypes suggests. Good-quality in-flight pictures of the pellets are reliably obtained by means of a video recording apparatus and a 20-ns pulsed flash lamp.<>
{"title":"Diagnostics of the high-speed single-pellet injector for the Frascati Tokamak Upgrade","authors":"E. Frattolillo, S. Migliori, F. Mirizzi, F. Scaramuzzi","doi":"10.1109/FUSION.1991.218653","DOIUrl":"https://doi.org/10.1109/FUSION.1991.218653","url":null,"abstract":"A diagnostic apparatus has been designed and tested, giving mass and speed measurements and in-flight pictures of the solid D/sub 2/ pellets for the high-speed (up to 3.3 km/s) single-pellet injector (SPIN) to be installed on the Frascati Tokamak Upgrade, (FTU), in order to completely characterize each of the launched pellets. A detailed description of the apparatus and of experimental results obtained with a prototype injector is given. From the point of view of speed determination, the system gives reliable results. Some problems have been detected on the volume (mass) determination, because the inner surfaces of the cavities have not been accurately treated for vacuum since they are prototypes. A new set of cavities is under construction and the whole setup will be improved according to what the experience with the prototypes suggests. Good-quality in-flight pictures of the pellets are reliably obtained by means of a video recording apparatus and a 20-ns pulsed flash lamp.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"13 3 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":"124263482","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}
Pub Date : 1991-09-30DOI: 10.1109/FUSION.1991.218791
A. Angelini, B. Coppi, M. Nassi
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>
{"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}
Pub Date : 1991-09-30DOI: 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
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.<>
{"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}
Pub Date : 1991-09-30DOI: 10.1109/FUSION.1991.218727
I. Yonekawa, M. Shimono, T. Totsuka, K. Yamagishi
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.<>
{"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}
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