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":"1 1","pages":"396-399"},"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.2002.1027657
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":"8 1","pages":"118-121"},"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.2002.1027687
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":"104 1","pages":"248-251"},"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}
An online trouble reporting system (TRS) has been introduced at NSTX. The TRS is used by NSTX operators to report problems that affect NSTX operations. The purpose of the TRS is to enhance NSTX reliability and maintainability by identifying components, occurrences, and trends that contribute to machine downtime. All NSTX personnel have access to the TRS. The user interface is via a Web browser, such as Netscape or Internet Explorer. This Web-based feature permits any X-terminal, PC, or MAC access to the TRS. The TRS is based upon a trouble reporting system developed at the DIII-D Tokamak, at General Atomics Technologies (Petersen and Miller, 1991). This paper provides a detailed description of the TRS software architecture, user interface, MS SQL server interface and operational experiences. In addition, sample data from the TRS database are summarized and presented.
{"title":"The NSTX trouble reporting system","authors":"S. Sengupta, G. Oliaro","doi":"10.2172/795714","DOIUrl":"https://doi.org/10.2172/795714","url":null,"abstract":"An online trouble reporting system (TRS) has been introduced at NSTX. The TRS is used by NSTX operators to report problems that affect NSTX operations. The purpose of the TRS is to enhance NSTX reliability and maintainability by identifying components, occurrences, and trends that contribute to machine downtime. All NSTX personnel have access to the TRS. The user interface is via a Web browser, such as Netscape or Internet Explorer. This Web-based feature permits any X-terminal, PC, or MAC access to the TRS. The TRS is based upon a trouble reporting system developed at the DIII-D Tokamak, at General Atomics Technologies (Petersen and Miller, 1991). This paper provides a detailed description of the TRS software architecture, user interface, MS SQL server interface and operational experiences. In addition, sample data from the TRS database are summarized and presented.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"13 1","pages":"242-244"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83808766","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":"5 1","pages":"272-275"},"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.2002.1027705
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":"2 1","pages":"333-336"},"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.2002.1027660
R. Ellis, J. Hosea, J. Wilson, L. Gereg, R. Prater, R. Callis, H. Grunloh
ECH launchers typically use a moveable mirror to steer a gyrotron beam. Increased power handling capability in an ECH launcher requires adding mass or active cooling to the mirrors. The additional forces on the moveable mirror resulting from either approach typically require a compromise between the power handling capability and the steering capability. The P2001 launcher, designed by PPPL for DIII-D, will launch two 800kW beams for 10 seconds every 10 minutes. Fully independent poloidal and toroidal steering during and between pulses, and a fast poloidal scan capability, will be provided. These design requirements are satisfied by the use of an innovative steering mechanism, which covers the entire scanning range about two axes and is strong enough to withstand the electromagnetic forces on the mirror. An innovative mirror design uses high thermal conductivity materials arranged in a manner that limits the eddy currents during a disruption. In this paper, the design of the P2001 launcher is presented, along with performance calculations. Design features relevant to advanced fusion experiments are highlighted and discussed.
{"title":"Design of the P2001 ECH launcher for DIII-D","authors":"R. Ellis, J. Hosea, J. Wilson, L. Gereg, R. Prater, R. Callis, H. Grunloh","doi":"10.1109/FUSION.2002.1027660","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027660","url":null,"abstract":"ECH launchers typically use a moveable mirror to steer a gyrotron beam. Increased power handling capability in an ECH launcher requires adding mass or active cooling to the mirrors. The additional forces on the moveable mirror resulting from either approach typically require a compromise between the power handling capability and the steering capability. The P2001 launcher, designed by PPPL for DIII-D, will launch two 800kW beams for 10 seconds every 10 minutes. Fully independent poloidal and toroidal steering during and between pulses, and a fast poloidal scan capability, will be provided. These design requirements are satisfied by the use of an innovative steering mechanism, which covers the entire scanning range about two axes and is strong enough to withstand the electromagnetic forces on the mirror. An innovative mirror design uses high thermal conductivity materials arranged in a manner that limits the eddy currents during a disruption. In this paper, the design of the P2001 launcher is presented, along with performance calculations. Design features relevant to advanced fusion experiments are highlighted and discussed.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"11 1","pages":"133-136"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91298336","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.2002.1027653
R. Walton, G. Agarici, G. Amarante, W. Baity, B. Beaumont, S. Bremond, F. Durodié, J. Fanthome, R. Goulding, J. Heikkinen, A. Kaye, R. Koch, P. Lamalle, G. Mazzone, J. Noterdaeme, V. Riccardo, M. Roccella, C. Sborchia, P. Testoni, P. Tigwell, K. Vulliez
The JET-EP antenna is designed to verify the design principles of that proposed for ITER, in relevant plasma conditions. It is intended to launch 7.2 MW of RF power to the plasma of the JET machine during its 'Enhanced Performance' program, at a power density of around 8 MW/m/sup 2/. The antenna comprises two poloidal current straps, each subdivided into four electrically short straps complete with in-vessel capacitors. The antenna is supported via a cantilever support box to the external support structure. This plug-in, through-port type assembly is clamped to the vacuum vessel externally. The antenna itself is fitted remotely. External rails and bellows allow radial positioning of the assembly. Eight capacitors are situated just behind the short antenna current straps. Plug-in replacement of the capacitors is performed through the vacuum vessel port.
{"title":"Mechanical design of the ICRH antenna for JET-EP","authors":"R. Walton, G. Agarici, G. Amarante, W. Baity, B. Beaumont, S. Bremond, F. Durodié, J. Fanthome, R. Goulding, J. Heikkinen, A. Kaye, R. Koch, P. Lamalle, G. Mazzone, J. Noterdaeme, V. Riccardo, M. Roccella, C. Sborchia, P. Testoni, P. Tigwell, K. Vulliez","doi":"10.1109/FUSION.2002.1027653","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027653","url":null,"abstract":"The JET-EP antenna is designed to verify the design principles of that proposed for ITER, in relevant plasma conditions. It is intended to launch 7.2 MW of RF power to the plasma of the JET machine during its 'Enhanced Performance' program, at a power density of around 8 MW/m/sup 2/. The antenna comprises two poloidal current straps, each subdivided into four electrically short straps complete with in-vessel capacitors. The antenna is supported via a cantilever support box to the external support structure. This plug-in, through-port type assembly is clamped to the vacuum vessel externally. The antenna itself is fitted remotely. External rails and bellows allow radial positioning of the assembly. Eight capacitors are situated just behind the short antenna current straps. Plug-in replacement of the capacitors is performed through the vacuum vessel port.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"22 1","pages":"103-106"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89456044","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.2002.1027639
M. Porfiri, P. Meloni
In the frame of the Safety and Environment tasks of the European Technology Program for ITER project one of the main issue is the validation of the computer codes and models used as reference for ITER safety analysis to obtain acceptance by licensing authorities. In the context of the fusion field facilities the data useful for validation are very limited because only few experimental machines are available as operating experience. To overcome this problem several integral and separate test experiments have been undertaken in the ITER program. The paper deals with the validation of the ISAS-ITER system for ITER safety analysis against the results obtained in the experimental campaign carried out during the year 2000 in the ICE (Ingress of Coolant Event) facility built in JAERI, Japan. ISAS-ITER links together the computer codes ATHENA (for thermal-hydraulic transient) and INTRA (for containment simulation). The experimental campaign investigated the discharge of water and steam from a pressurised container towards a vacuum vessel volume (VV) and a suppression tank. The VV represents the typical configuration of the plasma chamber, scaled respecting the geometrical dimensions of the ITER-FEAT design. Choked flow conditions, condensation, jet impingement and evaporation phenomena are involved in the tests reproducing different experimental conditions. ISAS-ITER post-test calculations, presented in the paper, show a quite good agreement with the ICE experimental data and the discussion of the results allows to detect the analytical model approximations that are the cause of the main discrepancies.
{"title":"Post-test calculations with ISAS-ITER system for ICE experiments","authors":"M. Porfiri, P. Meloni","doi":"10.1109/FUSION.2002.1027639","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027639","url":null,"abstract":"In the frame of the Safety and Environment tasks of the European Technology Program for ITER project one of the main issue is the validation of the computer codes and models used as reference for ITER safety analysis to obtain acceptance by licensing authorities. In the context of the fusion field facilities the data useful for validation are very limited because only few experimental machines are available as operating experience. To overcome this problem several integral and separate test experiments have been undertaken in the ITER program. The paper deals with the validation of the ISAS-ITER system for ITER safety analysis against the results obtained in the experimental campaign carried out during the year 2000 in the ICE (Ingress of Coolant Event) facility built in JAERI, Japan. ISAS-ITER links together the computer codes ATHENA (for thermal-hydraulic transient) and INTRA (for containment simulation). The experimental campaign investigated the discharge of water and steam from a pressurised container towards a vacuum vessel volume (VV) and a suppression tank. The VV represents the typical configuration of the plasma chamber, scaled respecting the geometrical dimensions of the ITER-FEAT design. Choked flow conditions, condensation, jet impingement and evaporation phenomena are involved in the tests reproducing different experimental conditions. ISAS-ITER post-test calculations, presented in the paper, show a quite good agreement with the ICE experimental data and the discussion of the results allows to detect the analytical model approximations that are the cause of the main discrepancies.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"18 1","pages":"48-51"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87868129","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":"33 1","pages":"260-263"},"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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