Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027705
P. Titus, J. Zaks, M. DeMaria, B. LaBombard, R. Granetz, J. Irby, B. Lipshultz, E. Fitzgerald, R. Childs, W. Beck, E. Marmar, D. Gwinn, I. Hutchinson, R. Boivin, W. Burke
In 1993 there were indications that the C-Mod inner divertor was being over-loaded. As a result, an inner divertor modification is being installed in C-Mod. The new design is intended to allow a change in profile of the divertor to accommodate a higher plasma triangularity, strengthen the inner vessel wall to survive 9.0 Tesla, 2.5 MA disruptions and, eliminate tile rotation. The thermal differentials between tiles and vessel wall, necessitated the introduction of compliance in the reinforcement hardware. Practical assembly within the vessel required manageable part size,and bolted interfaces which further reduced the strength and stiffness. A modest improvement of 22% was achieved while meeting the many design constraints.
{"title":"Alcator C-Mod inner divertor upgrade design and analysis","authors":"P. Titus, J. Zaks, M. DeMaria, B. LaBombard, R. Granetz, J. Irby, B. Lipshultz, E. Fitzgerald, R. Childs, W. Beck, E. Marmar, D. Gwinn, I. Hutchinson, R. Boivin, W. Burke","doi":"10.1109/FUSION.2002.1027705","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027705","url":null,"abstract":"In 1993 there were indications that the C-Mod inner divertor was being over-loaded. As a result, an inner divertor modification is being installed in C-Mod. The new design is intended to allow a change in profile of the divertor to accommodate a higher plasma triangularity, strengthen the inner vessel wall to survive 9.0 Tesla, 2.5 MA disruptions and, eliminate tile rotation. The thermal differentials between tiles and vessel wall, necessitated the introduction of compliance in the reinforcement hardware. Practical assembly within the vessel required manageable part size,and bolted interfaces which further reduced the strength and stiffness. A modest improvement of 22% was achieved while meeting the many design constraints.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86026951","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027721
N. Her, S. Cho, J. Sa, K. Im, G. Hong, G.H. Kim, J.Y. Park, H. Kim, B.C. Kim, I. Yu, D.L. Kim, W. Kim, Y. Oh, C. Choi, J. Bak, M. Kwon, G.S. Lee, J.H. Kim, H. Ahn
The KSTAR cryostat is a 8.8 m diameter vacuum vessel that provides the necessary thermal barrier between the ambient temperature test cell and the supercritical helium cooled superconducting magnet providing the base pressure of 1/spl times/10/sup -5/ torr. The cryostat is a single walled vessel consisting of central cylindrical section and two end closures, a flat base structure with external reinforcements and a dome-shaped lid structure. The base structure has 8 equally spaced support legs anchored on the concrete base. The cryostat vessel design was executed to satisfy the performance and operation requirements. The mechanical penetration components with bellows were designed to restrict the displacements of all kinds of ports due to EM loads and thermal loads within the allowable limits. The major loads considered in this paper for the design of cryostat vessel are the vacuum pressure, the dead weight of vacuum vessel, PFC, and magnet which are total about 400 tons, the electromagnetic load driven by plasma disruption, and seismic loads. Based on these loads, structural analyses were performed. It was found that the maximum stress intensity was below the allowable limit, and that the cryostat vessel had buckling safety of over 5. Based on the results, structural robustness of the cryostat vessel has been proved.
{"title":"Structural design and analysis for the KSTAR cryostat","authors":"N. Her, S. Cho, J. Sa, K. Im, G. Hong, G.H. Kim, J.Y. Park, H. Kim, B.C. Kim, I. Yu, D.L. Kim, W. Kim, Y. Oh, C. Choi, J. Bak, M. Kwon, G.S. Lee, J.H. Kim, H. Ahn","doi":"10.1109/FUSION.2002.1027721","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027721","url":null,"abstract":"The KSTAR cryostat is a 8.8 m diameter vacuum vessel that provides the necessary thermal barrier between the ambient temperature test cell and the supercritical helium cooled superconducting magnet providing the base pressure of 1/spl times/10/sup -5/ torr. The cryostat is a single walled vessel consisting of central cylindrical section and two end closures, a flat base structure with external reinforcements and a dome-shaped lid structure. The base structure has 8 equally spaced support legs anchored on the concrete base. The cryostat vessel design was executed to satisfy the performance and operation requirements. The mechanical penetration components with bellows were designed to restrict the displacements of all kinds of ports due to EM loads and thermal loads within the allowable limits. The major loads considered in this paper for the design of cryostat vessel are the vacuum pressure, the dead weight of vacuum vessel, PFC, and magnet which are total about 400 tons, the electromagnetic load driven by plasma disruption, and seismic loads. Based on these loads, structural analyses were performed. It was found that the maximum stress intensity was below the allowable limit, and that the cryostat vessel had buckling safety of over 5. Based on the results, structural robustness of the cryostat vessel has been proved.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82914727","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027693
M. Zaghloul, M. Tillack, T. Mau
Laser induced damage (LID) experiments were performed with a 2-J frequency-multiplied Nd:YAG laser at 1/2 /spl mu/m wavelength and a variety of metal mirrors (pure and impure diamond-turned) at shallow angle of incidence to study the sensitivity of these mirrors to LID under long term exposure. Practical lifetime curves for Al-1100 and 99.999% pure Al mirrors have been established up to 10/sup 4/ shots of operation. The results show general agreement with theoretical predictions.
{"title":"Laser-induced damage of metal mirrors under long-term exposure at shallow angle of incidence","authors":"M. Zaghloul, M. Tillack, T. Mau","doi":"10.1109/FUSION.2002.1027693","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027693","url":null,"abstract":"Laser induced damage (LID) experiments were performed with a 2-J frequency-multiplied Nd:YAG laser at 1/2 /spl mu/m wavelength and a variety of metal mirrors (pure and impure diamond-turned) at shallow angle of incidence to study the sensitivity of these mirrors to LID under long term exposure. Practical lifetime curves for Al-1100 and 99.999% pure Al mirrors have been established up to 10/sup 4/ shots of operation. The results show general agreement with theoretical predictions.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90112853","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027687
B. Nelson, R. Benson, L. Berry, A. Brooks, M. Cole, P.J. Fogrty, P. Goranson, P. Heitzenroeder, S. Hirschman, G. Jones, J. Lyon, P. Mioduszewski, D. Monticello, D. Spong, D. Strickler, A. Ware, D. Williamson
The engineering design status of the Quasi-Poloidal Stellarator Experiment (QPS) is presented. The purpose, configuration, and possible manufacturing and assembly techniques of the various components of the core are described.
{"title":"Design of the Quasi-Poloidal Stellarator Experiment (QPS)","authors":"B. Nelson, R. Benson, L. Berry, A. Brooks, M. Cole, P.J. Fogrty, P. Goranson, P. Heitzenroeder, S. Hirschman, G. Jones, J. Lyon, P. Mioduszewski, D. Monticello, D. Spong, D. Strickler, A. Ware, D. Williamson","doi":"10.1109/FUSION.2002.1027687","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027687","url":null,"abstract":"The engineering design status of the Quasi-Poloidal Stellarator Experiment (QPS) is presented. The purpose, configuration, and possible manufacturing and assembly techniques of the various components of the core are described.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75979199","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027630
F. Najmabadi
During the past ten years, the ARIES Team has studied a variety of tokamak power plants with different degrees of extrapolation in plasma physics and technology from present database. Continuation of research has allowed us to apply lessons learned from each ARIES design to the next. The results of ARIES tokamak power plant studies provide a large body of data that highlight the tradeoffs and relative leverage of advanced plasma physics and fusion technology directions. Our results indicate that for the same plasma physics (e.g., first-stability) and technology extrapolation, steady state operation is more attractive than pulsed-plasma operation. Dramatic improvement over first-stability operation can be obtained through either utilization of high-field magnets (e.g., high-temperature superconductors) or operation in advanced-tokamak modes (e.g., reversed-shear). In particular, if full benefits of reversed-shear operation are realized, as is assumed in ARIES-AT, tokamak power plants will have a cost of electricity competitive with other sources of electricity. In technology area, emerging technologies such as advanced Baryon cycle, high-temperature superconductor, and advanced manufacturing techniques can improve the cost and attractiveness of fusion plants. For blankets, liquid breeder/coolants are the most attractive because most of neutron power is directly deposited in the coolant. This property can be exploited to arrive at a blanket design with a coolant outlet temperature higher than the structure temperature in the radiation zone. The high coolant temperature leads to a high thermal conversion efficiency (as in ARIES-ST and ARIES-AT blankets). The dual-cooled (He and LiPb) ARIES-ST blanket using ferritic steel structural material represents a near-term option for fusion systems and achieves a thermal efficiency of 45%. Development of high-performance SIC composites leads to the high-performance ARIES-AT blanket (SiC composite/LiPb coolant) that achieves 59% thermal conversion efficiency as well as the full potential safety and environmental features of fusion power.
{"title":"Impact of advanced physics and technology on the attractiveness of tokamak fusion power plants","authors":"F. Najmabadi","doi":"10.1109/FUSION.2002.1027630","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027630","url":null,"abstract":"During the past ten years, the ARIES Team has studied a variety of tokamak power plants with different degrees of extrapolation in plasma physics and technology from present database. Continuation of research has allowed us to apply lessons learned from each ARIES design to the next. The results of ARIES tokamak power plant studies provide a large body of data that highlight the tradeoffs and relative leverage of advanced plasma physics and fusion technology directions. Our results indicate that for the same plasma physics (e.g., first-stability) and technology extrapolation, steady state operation is more attractive than pulsed-plasma operation. Dramatic improvement over first-stability operation can be obtained through either utilization of high-field magnets (e.g., high-temperature superconductors) or operation in advanced-tokamak modes (e.g., reversed-shear). In particular, if full benefits of reversed-shear operation are realized, as is assumed in ARIES-AT, tokamak power plants will have a cost of electricity competitive with other sources of electricity. In technology area, emerging technologies such as advanced Baryon cycle, high-temperature superconductor, and advanced manufacturing techniques can improve the cost and attractiveness of fusion plants. For blankets, liquid breeder/coolants are the most attractive because most of neutron power is directly deposited in the coolant. This property can be exploited to arrive at a blanket design with a coolant outlet temperature higher than the structure temperature in the radiation zone. The high coolant temperature leads to a high thermal conversion efficiency (as in ARIES-ST and ARIES-AT blankets). The dual-cooled (He and LiPb) ARIES-ST blanket using ferritic steel structural material represents a near-term option for fusion systems and achieves a thermal efficiency of 45%. Development of high-performance SIC composites leads to the high-performance ARIES-AT blanket (SiC composite/LiPb coolant) that achieves 59% thermal conversion efficiency as well as the full potential safety and environmental features of fusion power.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80140424","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027729
E. Schuster, M. Krstić, G. Tynan
Control of plasma density and temperature magnitudes, as well as their profiles, are among the most fundamental problems in fusion reactors. Unfortunately, the economy of fusion reactors often requires the reactor to operate under conditions in which the rate of thermonuclear reaction increases as the plasma temperature rises. In this thermally unstable zone, an active control system is necessary to stabilize the thermonuclear reaction. Existing efforts use control techniques for linear models. In this work, a zero-dimensional nonlinear model involving approximate conservation equations for the energy and the densities of the species was used to synthesize a nonlinear feedback controller for stabilizing the burn condition of a fusion reactor. The controller makes use simultaneously of the modulation of auxiliary power, the modulation of fueling rate and the controlled injection of impurities as actuators. A computer simulation study was performed to show the capability of the controller and compare it with previous linear controllers.
{"title":"Nonlinear burn control in fusion reactors","authors":"E. Schuster, M. Krstić, G. Tynan","doi":"10.1109/FUSION.2002.1027729","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027729","url":null,"abstract":"Control of plasma density and temperature magnitudes, as well as their profiles, are among the most fundamental problems in fusion reactors. Unfortunately, the economy of fusion reactors often requires the reactor to operate under conditions in which the rate of thermonuclear reaction increases as the plasma temperature rises. In this thermally unstable zone, an active control system is necessary to stabilize the thermonuclear reaction. Existing efforts use control techniques for linear models. In this work, a zero-dimensional nonlinear model involving approximate conservation equations for the energy and the densities of the species was used to synthesize a nonlinear feedback controller for stabilizing the burn condition of a fusion reactor. The controller makes use simultaneously of the modulation of auxiliary power, the modulation of fueling rate and the controlled injection of impurities as actuators. A computer simulation study was performed to show the capability of the controller and compare it with previous linear controllers.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73037787","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027657
T. Mau, M. Tillack, M. Zaghloul
Grazing incidence metal mirrors in laser-driven IFE power plants are subject to a variety of threats that result in damages leading to increased laser absorption, beam quality degradation and reduced laser-induced damage threshold. In this paper, we analyze the mirror reflectivity changes and wavefront distortions incident on the target using several modeling approaches, depending on the nature and size of the damage. We have developed a four-layer Fresnel solver to quantify the dependence of reflectivity on the thickness of surface contaminant and mirror protective coating, and their material properties, for a relevant range of incident angles. With a lossy contaminant like carbon, it is found that reflectivity decreases with thickness mainly due to surface dissipation, but this deleterious effect is diminished towards grazing incidence. For defect size small with respect to a wavelength, we have used Kerchhoff's wave scattering theory to evaluate degradation of the beam performance.
{"title":"Modeling of mirror surface damage effects on beam performance in a laser-driven IFE power plant","authors":"T. Mau, M. Tillack, M. Zaghloul","doi":"10.1109/FUSION.2002.1027657","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027657","url":null,"abstract":"Grazing incidence metal mirrors in laser-driven IFE power plants are subject to a variety of threats that result in damages leading to increased laser absorption, beam quality degradation and reduced laser-induced damage threshold. In this paper, we analyze the mirror reflectivity changes and wavefront distortions incident on the target using several modeling approaches, depending on the nature and size of the damage. We have developed a four-layer Fresnel solver to quantify the dependence of reflectivity on the thickness of surface contaminant and mirror protective coating, and their material properties, for a relevant range of incident angles. With a lossy contaminant like carbon, it is found that reflectivity decreases with thickness mainly due to surface dissipation, but this deleterious effect is diminished towards grazing incidence. For defect size small with respect to a wavelength, we have used Kerchhoff's wave scattering theory to evaluate degradation of the beam performance.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72635874","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027712
T. Shibata, T. Akiyama, N. Isei, H. Kawashima, H. Kimura, K. Miyachi, F. Okano, M. Sato, S. Suzuki, K. Tsuzuki, M. Yamamoto
On JFT-2M, to investigate whether low-activation ferritic steel (F82H) can be used as a structural material of the demonstration reactor, the Advanced Material Tokamak EXperiment (AMTEX) is being carried out step by step. The AMTEX program consists of three stages. In the 1st stage, the low-activation ferritic steel plates (FPs) were inserted between the vacuum vessel (VV) and the toroidal field coils (TFCs) to reduce the toroidal field ripple. In the 2nd stage, the pre-testing of compatibility with plasma was carried out by partially installing the FPs in the inside of VV. In the 3rd (final) stage, the testing of compatibility with plasma will be carried out by a full covering of the FPs on the inside of VV.
{"title":"Advanced Material Tokamak EXperiment (AMTEX) on JFT-2M - design, fabrication, installation and conditioning of inside ferritic steel wall","authors":"T. Shibata, T. Akiyama, N. Isei, H. Kawashima, H. Kimura, K. Miyachi, F. Okano, M. Sato, S. Suzuki, K. Tsuzuki, M. Yamamoto","doi":"10.1109/FUSION.2002.1027712","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027712","url":null,"abstract":"On JFT-2M, to investigate whether low-activation ferritic steel (F82H) can be used as a structural material of the demonstration reactor, the Advanced Material Tokamak EXperiment (AMTEX) is being carried out step by step. The AMTEX program consists of three stages. In the 1st stage, the low-activation ferritic steel plates (FPs) were inserted between the vacuum vessel (VV) and the toroidal field coils (TFCs) to reduce the toroidal field ripple. In the 2nd stage, the pre-testing of compatibility with plasma was carried out by partially installing the FPs in the inside of VV. In the 3rd (final) stage, the testing of compatibility with plasma will be carried out by a full covering of the FPs on the inside of VV.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73057066","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027650
Y. Srinivas, M. Kushwah, S. Kulkarni, K. Sathyanarayana, P. Khilar, B. Pal, P. Shah, A. Makwana, B. Kadia, K. Parmar, S. Dani, R. Singh, K. Parmar, D. Bora
Pulsed and continuous high power microwave tubes need to be protected against arc faults within the tube. If the energy dumped in such arc fault is more than the critical crater energy of the tube, irreparable damage can occur. Modern switch mode powers supplies (SMPS) that are generally opted for the new systems store little energy and are capable of switching HV in few microseconds. So they do not need separate protection. However, when conventional power supplies feed high power microwave tubes a reliable crowbar protection system, tested separately to limit the energy, must be used to assure the tube safety. Initial testing and commissioning of two klystrons, TH2103D have been carried out at our Institute. Each of these klystrons is capable of delivering 500 kW at 3.7 GHz, to be used for non-inductive lower hybrid current drive (LHCD) In the Steady-State Superconducting Tokamak-1 (SST-1). Commissioning of the gyrotron VGA8000A19, for breakdown and electron cyclotron resonant heating (ECRH) experiments on Aditya tokamak, has also been carried out.
{"title":"Results of 10-Joule wire-burn test performed on 70 kV rail-gap crowbar protection system for high power klystrons and gyrotron","authors":"Y. Srinivas, M. Kushwah, S. Kulkarni, K. Sathyanarayana, P. Khilar, B. Pal, P. Shah, A. Makwana, B. Kadia, K. Parmar, S. Dani, R. Singh, K. Parmar, D. Bora","doi":"10.1109/FUSION.2002.1027650","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027650","url":null,"abstract":"Pulsed and continuous high power microwave tubes need to be protected against arc faults within the tube. If the energy dumped in such arc fault is more than the critical crater energy of the tube, irreparable damage can occur. Modern switch mode powers supplies (SMPS) that are generally opted for the new systems store little energy and are capable of switching HV in few microseconds. So they do not need separate protection. However, when conventional power supplies feed high power microwave tubes a reliable crowbar protection system, tested separately to limit the energy, must be used to assure the tube safety. Initial testing and commissioning of two klystrons, TH2103D have been carried out at our Institute. Each of these klystrons is capable of delivering 500 kW at 3.7 GHz, to be used for non-inductive lower hybrid current drive (LHCD) In the Steady-State Superconducting Tokamak-1 (SST-1). Commissioning of the gyrotron VGA8000A19, for breakdown and electron cyclotron resonant heating (ECRH) experiments on Aditya tokamak, has also been carried out.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81233040","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027690
P. Sichta, G. Oliaro, S. Sengupta
Since 1988, the Tritium Remote Control and Monitoring System (TRECAMS) has performed crucial functions in support of D-T operations of the Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory (PPPL). Although plasma operations on TFTR were completed in 1997, the need for TRECAMS continued. During this period TRECAMS supported the TFTR tritium systems, the TFTR's shutdown and safing phase, and the TFTR Decontamination and Decommissioning (D&D) project. The most critical function of the TRECAMS in the post-TFTR era has been to provide a real-time indication of the airborne tritium levels in the tritium areas and the (HVAC) stacks. TRECAMS is a critical tool in conducting safe TFTR D&D tritium-line breaks and other tritium-related work activities.
{"title":"Upgrade to the Tritium Remote Control and Monitoring System for TFTR D&D","authors":"P. Sichta, G. Oliaro, S. Sengupta","doi":"10.1109/FUSION.2002.1027690","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027690","url":null,"abstract":"Since 1988, the Tritium Remote Control and Monitoring System (TRECAMS) has performed crucial functions in support of D-T operations of the Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory (PPPL). Although plasma operations on TFTR were completed in 1997, the need for TRECAMS continued. During this period TRECAMS supported the TFTR tritium systems, the TFTR's shutdown and safing phase, and the TFTR Decontamination and Decommissioning (D&D) project. The most critical function of the TRECAMS in the post-TFTR era has been to provide a real-time indication of the airborne tritium levels in the tritium areas and the (HVAC) stacks. TRECAMS is a critical tool in conducting safe TFTR D&D tritium-line breaks and other tritium-related work activities.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":null,"pages":null},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90438534","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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