Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027697
S. Wukitch, W. Beck, E. Fitzgerald, R. Granetz, D. Gwinn, M. Grimes, J. Irby, E. Marmar, D. Terry, P. Titus, R. Vieira, S. Wolfe, J. Zaks, S. Bernabei, R. Ellis, L. Gereg, J. Hosea, D. Loesser, G. Schilling, J. Wilson
Recent Alcator C-Mod experimental campaigns have focused upon the study of the Advanced Tokamak regimes, which includes characterization of the RF heating, the formation and dynamics of internal barriers, H-mode edge pedestal, and divertor and scrape-off physics. The ICRF system has been recently upgraded with the improved performance of the 4-strap antenna. Total ICRF power in excess of 5 MW has been launched successfully into the plasma during this campaign. Due to the compact nature of C-Mod, the power feeds for the antenna are vacuum strip lines. Their orientation, to the tokamak B-field, is governed by maintaining E<15 kV/cm in locations where the RF E-field is parallel to tokamak B-field. Other modifications included improved protection tile grounding and installation of protective shields for Faraday screen ceramic isolators. The antennas also make use of BN protection tiles to eliminate high Z impurities from the antennas. The present empirical power limit results from arcing in a region of the antenna strap where E/spl sim/15 kV/cm and parallel to B and injections from the metallic fasteners used to attach the BN tiles to the antenna.
{"title":"Results and status of the Alcator C-Mod tokamak","authors":"S. Wukitch, W. Beck, E. Fitzgerald, R. Granetz, D. Gwinn, M. Grimes, J. Irby, E. Marmar, D. Terry, P. Titus, R. Vieira, S. Wolfe, J. Zaks, S. Bernabei, R. Ellis, L. Gereg, J. Hosea, D. Loesser, G. Schilling, J. Wilson","doi":"10.1109/FUSION.2002.1027697","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027697","url":null,"abstract":"Recent Alcator C-Mod experimental campaigns have focused upon the study of the Advanced Tokamak regimes, which includes characterization of the RF heating, the formation and dynamics of internal barriers, H-mode edge pedestal, and divertor and scrape-off physics. The ICRF system has been recently upgraded with the improved performance of the 4-strap antenna. Total ICRF power in excess of 5 MW has been launched successfully into the plasma during this campaign. Due to the compact nature of C-Mod, the power feeds for the antenna are vacuum strip lines. Their orientation, to the tokamak B-field, is governed by maintaining E<15 kV/cm in locations where the RF E-field is parallel to tokamak B-field. Other modifications included improved protection tile grounding and installation of protective shields for Faraday screen ceramic isolators. The antennas also make use of BN protection tiles to eliminate high Z impurities from the antennas. The present empirical power limit results from arcing in a region of the antenna strap where E/spl sim/15 kV/cm and parallel to B and injections from the metallic fasteners used to attach the BN tiles to the antenna.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"4 1","pages":"290-295"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72660976","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.2002.1027649
B. Shukla, K. Sathyanarayana, D. Bora, S. Rajashree, K. Bhattacharya, B. Pal, S. Kulkarni, S. Gangopadhyay, Y. Srinivas, P. Khilar, M. Kushwah, R. Trivedi, D. Rathi, B. Kadia, A. Patel, C. Virani, P. Harsida, H. M. Jadav, K. Parmar, P. Shah, A. Makwana, S. Dani, P. Kirit, M. Harsha, J. Soni
A 28 GHz ECRH system has been successfully commissioned on the tokamak Aditya to carry out breakdown, start up and heating experiments. The microwave source gyrotron VGA8000A19 capable of delivering 200 kW CW is commissioned and tested with a water dummy load for pulsed operation. The output mode of the gyrotron (TE/sub 02/) is externally converted to the HE/sub 11/ mode with the help of a mode converter and Matching Optics Unit of the transmission line. The transmission line consists of a mode converter, MOU, DC breaks, mitre bend, polarizer unit and different sizes of corrugated waveguides. The total transmission loss of the transmission line including 10 m long waveguides is measured to be less than 1.1 dB. The burn patterns at different locations of the transmission line confirm the mode purity to be better than 93% in the TE/sub 02/ mode. The transmission line terminates at a launcher box through a barrier window. The ECRH launcher consists of two mirrors to focus the microwave beam at the plasma center. The first mirror is convex while the second mirror is a concave focusing mirror. The mirrors are designed based on quasi optical analysis of the launcher system. The focal length of second mirror is 392.9 mm, which focuses the microwave beam to 35 mm (beam waist radius) at the plasma center. Beam steering in the plasma volume is restricted to /spl plusmn/2/spl deg/. The gyrotron is tested up to /spl sim/80 kW output power. A hard-wired interlock for various fault conditions, operates a rail-gap crowbar in less than 10 /spl mu/S to protect the gyrotron. The gyrotron output is coupled to the tokamak Aditya (O-mode, perpendicular launch from low field side) and successful breakdown of the neutral gas is observed at different tokamak parameters. The paper describes the technical aspects of commissioning of the ECRH system and breakdown results on Aditya.
{"title":"Electron cyclotron resonance frequency system on tokamak Aditya","authors":"B. Shukla, K. Sathyanarayana, D. Bora, S. Rajashree, K. Bhattacharya, B. Pal, S. Kulkarni, S. Gangopadhyay, Y. Srinivas, P. Khilar, M. Kushwah, R. Trivedi, D. Rathi, B. Kadia, A. Patel, C. Virani, P. Harsida, H. M. Jadav, K. Parmar, P. Shah, A. Makwana, S. Dani, P. Kirit, M. Harsha, J. Soni","doi":"10.1109/FUSION.2002.1027649","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027649","url":null,"abstract":"A 28 GHz ECRH system has been successfully commissioned on the tokamak Aditya to carry out breakdown, start up and heating experiments. The microwave source gyrotron VGA8000A19 capable of delivering 200 kW CW is commissioned and tested with a water dummy load for pulsed operation. The output mode of the gyrotron (TE/sub 02/) is externally converted to the HE/sub 11/ mode with the help of a mode converter and Matching Optics Unit of the transmission line. The transmission line consists of a mode converter, MOU, DC breaks, mitre bend, polarizer unit and different sizes of corrugated waveguides. The total transmission loss of the transmission line including 10 m long waveguides is measured to be less than 1.1 dB. The burn patterns at different locations of the transmission line confirm the mode purity to be better than 93% in the TE/sub 02/ mode. The transmission line terminates at a launcher box through a barrier window. The ECRH launcher consists of two mirrors to focus the microwave beam at the plasma center. The first mirror is convex while the second mirror is a concave focusing mirror. The mirrors are designed based on quasi optical analysis of the launcher system. The focal length of second mirror is 392.9 mm, which focuses the microwave beam to 35 mm (beam waist radius) at the plasma center. Beam steering in the plasma volume is restricted to /spl plusmn/2/spl deg/. The gyrotron is tested up to /spl sim/80 kW output power. A hard-wired interlock for various fault conditions, operates a rail-gap crowbar in less than 10 /spl mu/S to protect the gyrotron. The gyrotron output is coupled to the tokamak Aditya (O-mode, perpendicular launch from low field side) and successful breakdown of the neutral gas is observed at different tokamak parameters. The paper describes the technical aspects of commissioning of the ECRH system and breakdown results on Aditya.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"26 1","pages":"88-90"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83847489","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.2002.1027654
N. Taylor
The neutron shielding provided by in-vessel components of a fusion power plant has an important influence on the safety and environmental performance. A number of issues related to the in-vessel shield design have been investigated, with a focus on waste minimization. Viable concepts have been identified to solve the conflict between low short-term decay heat and low long-term waste requirements, and for shields avoiding water coolant in plant designs employing beryllium neutron multiplier.
{"title":"Safety and environmental considerations in the selection of fusion power plant design options","authors":"N. Taylor","doi":"10.1109/FUSION.2002.1027654","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027654","url":null,"abstract":"The neutron shielding provided by in-vessel components of a fusion power plant has an important influence on the safety and environmental performance. A number of issues related to the in-vessel shield design have been investigated, with a focus on waste minimization. Viable concepts have been identified to solve the conflict between low short-term decay heat and low long-term waste requirements, and for shields avoiding water coolant in plant designs employing beryllium neutron multiplier.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"2 1","pages":"107-110"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81384190","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.2002.1027659
J. Lohr, S. Delaware, R. Callis, W. Cary, J. Deboo, J. Doane, I. Gorelov, R. L. La Haye, H. Grunloh, C. Petty, R. Pinsker, D. Ponce, R. Prater, S. Pronko
Advances in gyrotron technology are resulting in new capabilities and scientific results on magnetic confinement devices for fusion research worldwide. Unit output power of 1 MW and higher, at frequencies greater than 100 GHz and quasi-cw operation have become possible. This has led to successful experiments on electron cyclotron heating, electron cyclotron current drive, non-inductive tokamak operation, tokamak energy transport, suppression of instabilities and advanced profile control leading to enhanced performance. The synthetic diamond gyrotron output window is being developed as the answer to the requirement for a low loss blocking window with excellent thermal and mechanical properties and the potential for cw operation at high power. Ancillary equipment for efficient microwave transmission over distances of hundreds of meters, polarization control, diagnostics and flexible launch geometry have all been developed and proven in regular service. There now is excellent convergence between the experimental measurements and theoretical understanding of the heating and current drive mechanisms. The reliability of high power gyrotron installations is at the level previously achieved by neutral beam systems.
{"title":"ECH comes of age for magnetic fusion research","authors":"J. Lohr, S. Delaware, R. Callis, W. Cary, J. Deboo, J. Doane, I. Gorelov, R. L. La Haye, H. Grunloh, C. Petty, R. Pinsker, D. Ponce, R. Prater, S. Pronko","doi":"10.1109/FUSION.2002.1027659","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027659","url":null,"abstract":"Advances in gyrotron technology are resulting in new capabilities and scientific results on magnetic confinement devices for fusion research worldwide. Unit output power of 1 MW and higher, at frequencies greater than 100 GHz and quasi-cw operation have become possible. This has led to successful experiments on electron cyclotron heating, electron cyclotron current drive, non-inductive tokamak operation, tokamak energy transport, suppression of instabilities and advanced profile control leading to enhanced performance. The synthetic diamond gyrotron output window is being developed as the answer to the requirement for a low loss blocking window with excellent thermal and mechanical properties and the potential for cw operation at high power. Ancillary equipment for efficient microwave transmission over distances of hundreds of meters, polarization control, diagnostics and flexible launch geometry have all been developed and proven in regular service. There now is excellent convergence between the experimental measurements and theoretical understanding of the heating and current drive mechanisms. The reliability of high power gyrotron installations is at the level previously achieved by neutral beam systems.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"40 1","pages":"126-132"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83581676","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}
The Fusion Summer Study 2002 will be a forum for the critical technical assessment of major next-steps in the fusion energy sciences program, and will provide crucial community input to the long-range planning activities undertaken by the DOE and the FESAC. It will be an ideal place for a broad community of scientists to examine goals and proposed initiatives in burning plasma science in magnetic fusion energy and integrated research experiments in inertial fusion energy. This meeting is open to every member of the fusion energy science community and significant international participation is encouraged. The objectives of the Fusion Summer Study are three: 1. Review scientific issues in burning plasmas to establish the basis for the following two objectives and to address the relations of burning plasma in tokamaks to innovative magnetic fusion energy (MFE) confinement concepts and of ignition in inertial fusion energy (IFE) to integrated research facilities. 2. Provide a forum for critical discussion and review of proposed MFE burning plasma experiments (e.g., IGNITOR, FIRE, and ITER) and assess the scientific and technological research opportunities and prospective benefits of these approaches to the study of burning plasmas. 3. Provide a forum for the IFE community to present plans for prospective integrated research facilities, assess present status of the technical base for each, and establish a timetable and technical progress necessary to proceed for each. Based on significant preparatory work by the fusion community prior to the July Snowmass meeting, the Snowmass working groups will prepare a draft report that documents the scientific and technological benefits of studies of burning plasmas. The report will also include criteria by which the benefits of each approach to fusion science, fusion engineering/technology, and the fusion development path can be assessed. Finally, the report will present a uniform technical assessment of the benefits of the three approaches. The draft report will be presented and extensively discussed during the July meeting, leading to a final report. This report will provide critical fusion community input to the decision process of FESAC and DOE in 2002-2003, and to the review of burning plasma science by the National Academy of Sciences called for by FESAC and Energy Legislation which was passed by the House of Representatives. Members of the fusion community are encouraged to participate in the Snowmass working groups.
{"title":"Snowmass 2002: the fusion energy sciences summer study","authors":"N. Sauthoff, G. Navratil, R. Bangerter","doi":"10.2172/795778","DOIUrl":"https://doi.org/10.2172/795778","url":null,"abstract":"The Fusion Summer Study 2002 will be a forum for the critical technical assessment of major next-steps in the fusion energy sciences program, and will provide crucial community input to the long-range planning activities undertaken by the DOE and the FESAC. It will be an ideal place for a broad community of scientists to examine goals and proposed initiatives in burning plasma science in magnetic fusion energy and integrated research experiments in inertial fusion energy. This meeting is open to every member of the fusion energy science community and significant international participation is encouraged. The objectives of the Fusion Summer Study are three: 1. Review scientific issues in burning plasmas to establish the basis for the following two objectives and to address the relations of burning plasma in tokamaks to innovative magnetic fusion energy (MFE) confinement concepts and of ignition in inertial fusion energy (IFE) to integrated research facilities. 2. Provide a forum for critical discussion and review of proposed MFE burning plasma experiments (e.g., IGNITOR, FIRE, and ITER) and assess the scientific and technological research opportunities and prospective benefits of these approaches to the study of burning plasmas. 3. Provide a forum for the IFE community to present plans for prospective integrated research facilities, assess present status of the technical base for each, and establish a timetable and technical progress necessary to proceed for each. Based on significant preparatory work by the fusion community prior to the July Snowmass meeting, the Snowmass working groups will prepare a draft report that documents the scientific and technological benefits of studies of burning plasmas. The report will also include criteria by which the benefits of each approach to fusion science, fusion engineering/technology, and the fusion development path can be assessed. Finally, the report will present a uniform technical assessment of the benefits of the three approaches. The draft report will be presented and extensively discussed during the July meeting, leading to a final report. This report will provide critical fusion community input to the decision process of FESAC and DOE in 2002-2003, and to the review of burning plasma science by the National Academy of Sciences called for by FESAC and Energy Legislation which was passed by the House of Representatives. Members of the fusion community are encouraged to participate in the Snowmass working groups.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"20 1","pages":"156-158"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82436608","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.2002.1027652
N. Greenough, S. Depasquale, D. Lafrance
Recent developments in programmable logic devices have led to in-system programming capabilities for FPGA (field programmable logic array) and CPLD (complex programmable logic device) devices using inexpensive programming heads and PC-type computers. This development has major advantages for electronic equipment used in a research setting. Many of the devices are electrically erasable and re-programmable hundreds or thousands of times, allowing fast in-system circuit changes or error-correction in the field. This paper describes the successful application of a programmable logic device to a multi-channel phase detector for the HHFW RF systems on NSTX.
{"title":"A multi-channel phase detector using programmable logic devices","authors":"N. Greenough, S. Depasquale, D. Lafrance","doi":"10.1109/FUSION.2002.1027652","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027652","url":null,"abstract":"Recent developments in programmable logic devices have led to in-system programming capabilities for FPGA (field programmable logic array) and CPLD (complex programmable logic device) devices using inexpensive programming heads and PC-type computers. This development has major advantages for electronic equipment used in a research setting. Many of the devices are electrically erasable and re-programmable hundreds or thousands of times, allowing fast in-system circuit changes or error-correction in the field. This paper describes the successful application of a programmable logic device to a multi-channel phase detector for the HHFW RF systems on NSTX.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"108 1","pages":"99-102"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79219394","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.2002.1027707
R. Majeski, G. Antar, M. Boaz, D. Buchenauer, L. Cadwallader, R. Causey, R. Conn, R. Doerner, P. Efthimion, M. Finkenthal, D. Hoffman, B. Jones, R. Kaita, H. Kugel, S. Luckhardt, R. Maingi, M. Maiorano, T. Munsat, S. Raftopoulos, T. Rognlein, J. Spaleta, V. Soukhanovskii, D. Stutman, G. Taylor, J. Timberlake, M. Ulrickson, D. Whyte
Attention has focused recently on flowing liquid lithium as a first wall for a reactor because of its potentially attractive physics and engineering features. In order to test the suitability of liquid lithium as a plasma facing component, the Current Drive eXperiment - Upgrade (CDX-U) at the Princeton Plasma Physics Laboratory has recently installed a fully toroidal liquid lithium limiter. CDX-U is a compact (R = 34 cm, a = 22 cm, B/sub toroidal/ = 2 kG, I/sub p/ =100 kA, T/sub e/(O) /spl sim/ 100 eV, n/sub e/(0) /spl sim/ 5 /spl times/ 10/sup 19/ m/sup -3/ short-pulse (< 25 msec) spherical torus (ST) with extensive diagnostics. The limiter, which consists of a shallow circular stainless steel tray of radius 34 cm and width 10 cm, is filled with lithium to a depth of a few millimeters, and forms the lower limiting surface for the discharge. Heating elements beneath the tray are used to liquefy the lithium (melting point = 180.5/spl deg/C) prior to the experiment. The total area of liquid lithium exposed to the plasma is approximately 2000 cm/sup 2/. The design of the limiter, modifications to CDX-U to accommodate in-vessel inventories of approximately 1 liter of liquid lithium, techniques for loading lithium onto the limiter, and other preparations will be described. CDX-U has previously been successfully operated with a smaller area cm/sup 2/) liquid lithium rail limiter. Diagnostics specific to lithium operations include multichord spectrometry of the 135 /spl Aring/ LiIII line in the core plasma, monitors for neutral lithium light at the lithium limiter, and a fast (10,000 frame per second) camera which monitors motion of the liquid during the discharge. First results of plasma operations with the toroidal liquid lithium limiter will also be given.
{"title":"A toroidal liquid lithium limiter for CDX-U","authors":"R. Majeski, G. Antar, M. Boaz, D. Buchenauer, L. Cadwallader, R. Causey, R. Conn, R. Doerner, P. Efthimion, M. Finkenthal, D. Hoffman, B. Jones, R. Kaita, H. Kugel, S. Luckhardt, R. Maingi, M. Maiorano, T. Munsat, S. Raftopoulos, T. Rognlein, J. Spaleta, V. Soukhanovskii, D. Stutman, G. Taylor, J. Timberlake, M. Ulrickson, D. Whyte","doi":"10.1109/FUSION.2002.1027707","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027707","url":null,"abstract":"Attention has focused recently on flowing liquid lithium as a first wall for a reactor because of its potentially attractive physics and engineering features. In order to test the suitability of liquid lithium as a plasma facing component, the Current Drive eXperiment - Upgrade (CDX-U) at the Princeton Plasma Physics Laboratory has recently installed a fully toroidal liquid lithium limiter. CDX-U is a compact (R = 34 cm, a = 22 cm, B/sub toroidal/ = 2 kG, I/sub p/ =100 kA, T/sub e/(O) /spl sim/ 100 eV, n/sub e/(0) /spl sim/ 5 /spl times/ 10/sup 19/ m/sup -3/ short-pulse (< 25 msec) spherical torus (ST) with extensive diagnostics. The limiter, which consists of a shallow circular stainless steel tray of radius 34 cm and width 10 cm, is filled with lithium to a depth of a few millimeters, and forms the lower limiting surface for the discharge. Heating elements beneath the tray are used to liquefy the lithium (melting point = 180.5/spl deg/C) prior to the experiment. The total area of liquid lithium exposed to the plasma is approximately 2000 cm/sup 2/. The design of the limiter, modifications to CDX-U to accommodate in-vessel inventories of approximately 1 liter of liquid lithium, techniques for loading lithium onto the limiter, and other preparations will be described. CDX-U has previously been successfully operated with a smaller area cm/sup 2/) liquid lithium rail limiter. Diagnostics specific to lithium operations include multichord spectrometry of the 135 /spl Aring/ LiIII line in the core plasma, monitors for neutral lithium light at the lithium limiter, and a fast (10,000 frame per second) camera which monitors motion of the liquid during the discharge. First results of plasma operations with the toroidal liquid lithium limiter will also be given.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"25 1","pages":"341-344"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80975933","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.2002.1027691
J. Feist
WENDELSTEIN 7-X, being under construction at the Greifswald branch of the Max-Planck-Institut fur Plasmaphysik, has the objective to prove the reactor relevance of a HELIAS type stellarator. Energy and particle confinement will be investigated in an optimised magnetic configuration and stationary operation of a reactor relevant divertor system will be demonstrated. After an intensive R&D program, the project is in the phase of procurement of the main components. This holds for the magnet system, the cryostat, the in-vessel components, the heating systems as well as for various tools for the assembly. Start of operation is scheduled for 2006.
{"title":"Status of WENDELSTEIN 7-X construction","authors":"J. Feist","doi":"10.1109/FUSION.2002.1027691","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027691","url":null,"abstract":"WENDELSTEIN 7-X, being under construction at the Greifswald branch of the Max-Planck-Institut fur Plasmaphysik, has the objective to prove the reactor relevance of a HELIAS type stellarator. Energy and particle confinement will be investigated in an optimised magnetic configuration and stationary operation of a reactor relevant divertor system will be demonstrated. After an intensive R&D program, the project is in the phase of procurement of the main components. This holds for the magnet system, the cryostat, the in-vessel components, the heating systems as well as for various tools for the assembly. Start of operation is scheduled for 2006.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"25 1","pages":"264-267"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89512459","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.2002.1027708
R. Nygren, D. Youchison, J. Kim, K. Im, K.S. Kim, H.C. Park
Uncooled samples of various carbon fiber composites (CFCs), nominally 2.50 cm square and 1.00 cm in height were exposed in the Electron Beam Test System (EBTS) to heat fluxes up to /spl sim/100 MW/m/sup 2/ for shots typically of 1.5 s. The heat flux was focused on a square 1 /spl times/ 1 cm at the center of the sample. For NSTX (National Spherical Torus Experiment), five samples of Allied Signal 2-D CFC Type 865-19-4 were tested with 1.5 s shots at heat fluxes to 120 MW/m/sup 2/. For KSTAR (Korean Superconducting Tokamak Advanced Research) Project, a total of 37 samples of 29 various CFCs were tested. Duplicates samples with thermocouples were used to measure the absorbed heat and to calculate the fraction of the beam power absorbed. The samples were tested to 100 MW/m/sup 2/ with 1.5 s shots and then selected samples were tested at 60 MW/m/sup 2/ for shots up to 3.5 s. The most basic results from all of these tests is that, as expected, none of the samples fractured. For the KSTAR test, some samples achieved higher heat fluxes than others while their surface temperatures remained below a threshold of 2800/spl deg/C. Other observations presented in the paper are based on post-test examinations of the surface morphologies. The paper was presented in poster form at SOFE99 but not published there and is represented here.
{"title":"High heat flux tests of carbon composites for KSTAR and NSTX","authors":"R. Nygren, D. Youchison, J. Kim, K. Im, K.S. Kim, H.C. Park","doi":"10.1109/FUSION.2002.1027708","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027708","url":null,"abstract":"Uncooled samples of various carbon fiber composites (CFCs), nominally 2.50 cm square and 1.00 cm in height were exposed in the Electron Beam Test System (EBTS) to heat fluxes up to /spl sim/100 MW/m/sup 2/ for shots typically of 1.5 s. The heat flux was focused on a square 1 /spl times/ 1 cm at the center of the sample. For NSTX (National Spherical Torus Experiment), five samples of Allied Signal 2-D CFC Type 865-19-4 were tested with 1.5 s shots at heat fluxes to 120 MW/m/sup 2/. For KSTAR (Korean Superconducting Tokamak Advanced Research) Project, a total of 37 samples of 29 various CFCs were tested. Duplicates samples with thermocouples were used to measure the absorbed heat and to calculate the fraction of the beam power absorbed. The samples were tested to 100 MW/m/sup 2/ with 1.5 s shots and then selected samples were tested at 60 MW/m/sup 2/ for shots up to 3.5 s. The most basic results from all of these tests is that, as expected, none of the samples fractured. For the KSTAR test, some samples achieved higher heat fluxes than others while their surface temperatures remained below a threshold of 2800/spl deg/C. Other observations presented in the paper are based on post-test examinations of the surface morphologies. The paper was presented in poster form at SOFE99 but not published there and is represented here.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"19 1","pages":"345-347"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87377538","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.2002.1027694
S. Ishida
Recently, JT-60U has intensively addressed enhancement and long sustainment of steady state performance in the use of negative-ion based neutral beam injection (N-NBI) and electron cyclotron (EC) wave injection. The N-NBI increased the current drive efficiency up to 1.55/spl times/10/sup 19/ A/m/sup 2//W at 360 keV and enhanced the fusion triple product up to n/sub i/(0)/spl tau//sub E/T/sub l/(0)/spl sim/3.0/spl times/10/sup 20/ keV sm/sup -3/ during, a full current drive condition. Increasing the plasma triangularity extended the duration of a plasma with /spl beta//sub N//spl sim/2.7 up to /spl sim/60 /spl tau//sub E/. The EC heating in combination with lower hybrid wave injection produced a very high electron temperature of /spl sim/26 keV for a reversed shear plasma. For reversed shear plasmas, the formation and sustainment of a central current hole was also discovered. High-field-side pellet injection extended the confinement up to H/sub 89p//spl sim/2 at n/n/sub G//spl sim/0.7. For the modification of JT-60, a fully superconducting tokamak, JT-60SC, is planned to further economical and environmental attractiveness in a tokamak DEMO reactor. The mission of JT-60SC is to realize high performance steady state operation and demonstrate the plasma applicability of low activation material for a plasma of break-even class relevant to the reactor plasma. Physics issues, design and machine description for JT-60SC with I/sub p/=4 MA, B/sub t/=3.8 T and R/sub p/=2.8 in are outlined.
{"title":"Recent results and future plan on JT-60U","authors":"S. Ishida","doi":"10.1109/FUSION.2002.1027694","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027694","url":null,"abstract":"Recently, JT-60U has intensively addressed enhancement and long sustainment of steady state performance in the use of negative-ion based neutral beam injection (N-NBI) and electron cyclotron (EC) wave injection. The N-NBI increased the current drive efficiency up to 1.55/spl times/10/sup 19/ A/m/sup 2//W at 360 keV and enhanced the fusion triple product up to n/sub i/(0)/spl tau//sub E/T/sub l/(0)/spl sim/3.0/spl times/10/sup 20/ keV sm/sup -3/ during, a full current drive condition. Increasing the plasma triangularity extended the duration of a plasma with /spl beta//sub N//spl sim/2.7 up to /spl sim/60 /spl tau//sub E/. The EC heating in combination with lower hybrid wave injection produced a very high electron temperature of /spl sim/26 keV for a reversed shear plasma. For reversed shear plasmas, the formation and sustainment of a central current hole was also discovered. High-field-side pellet injection extended the confinement up to H/sub 89p//spl sim/2 at n/n/sub G//spl sim/0.7. For the modification of JT-60, a fully superconducting tokamak, JT-60SC, is planned to further economical and environmental attractiveness in a tokamak DEMO reactor. The mission of JT-60SC is to realize high performance steady state operation and demonstrate the plasma applicability of low activation material for a plasma of break-even class relevant to the reactor plasma. Physics issues, design and machine description for JT-60SC with I/sub p/=4 MA, B/sub t/=3.8 T and R/sub p/=2.8 in are outlined.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"1 1","pages":"276-281"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86470593","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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