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":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":"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":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":"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.2002.1027689
B. Doshi, K.J. Thomas, S. Das, R. kumar E., Y. Saxena
SST-1 is a large aspect ratio tokamak designed for steady state operation, configured to run a double/single null, elongated triangular plasma, which is under construction in India. It has a major radius of 1.1 m with plasma minor radius of 0.2 m, with maximum toroidal magnetic field 3 Tesla at the plasma center. SST-1 tokamak has a large number of components to be assembled at site to build various systems like machine support structure, plasma chamber, cryostat, magnet system, first wall (PFC) and other auxiliary systems. In this device the required assembly tolerances are in the order of several tenth of a millimeter. The tight installation tolerances, definite assembly sequences and process restrictions govern the efficacy of the assembly procedures. SST-1 assembly demands definite sequence to be followed to ensure sequential testing of each system, accurate positioning of the components in the radial, toroidal, poloidal and vertical direction to meet the tolerances and magnetic axis determination and alignment of the plasma facing components.
{"title":"Assembly, integration and dimensional control of the steady state tokamak SST-1","authors":"B. Doshi, K.J. Thomas, S. Das, R. kumar E., Y. Saxena","doi":"10.1109/FUSION.2002.1027689","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027689","url":null,"abstract":"SST-1 is a large aspect ratio tokamak designed for steady state operation, configured to run a double/single null, elongated triangular plasma, which is under construction in India. It has a major radius of 1.1 m with plasma minor radius of 0.2 m, with maximum toroidal magnetic field 3 Tesla at the plasma center. SST-1 tokamak has a large number of components to be assembled at site to build various systems like machine support structure, plasma chamber, cryostat, magnet system, first wall (PFC) and other auxiliary systems. In this device the required assembly tolerances are in the order of several tenth of a millimeter. The tight installation tolerances, definite assembly sequences and process restrictions govern the efficacy of the assembly procedures. SST-1 assembly demands definite sequence to be followed to ensure sequential testing of each system, accurate positioning of the components in the radial, toroidal, poloidal and vertical direction to meet the tolerances and magnetic axis determination and alignment of the plasma facing components.","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":"81020564","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.2002.1027661
C. Baxi, M. Friend, J. Doane, E. Reis, R. Callis
Each GA ECH launcher mirrors is used to transmit 800 kW of power to the plasma. Until 2000, the pulse length for use of these mirrors was limited to 2 s due to temperatures of the mirrors resulting from 1) a high ratcheted bulk temperature and 2) a large increase in temperature of the mirror during the pulse. A new design was proposed and implemented which has extended the capability of the mirror to 10 s with passive cooling. The important features of the new design are 1) increase in the passive heat transfer rate during cooling and 2) a modified shape of the mirror. The analysis shows that, the new mirrors can be used for 10 s pulses. The new mirrors have been installed in DIII-D, they have been used for up to 2 s pulses.
{"title":"Thermal design of GA ECH launcher mirror for long pulse operation","authors":"C. Baxi, M. Friend, J. Doane, E. Reis, R. Callis","doi":"10.1109/FUSION.2002.1027661","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027661","url":null,"abstract":"Each GA ECH launcher mirrors is used to transmit 800 kW of power to the plasma. Until 2000, the pulse length for use of these mirrors was limited to 2 s due to temperatures of the mirrors resulting from 1) a high ratcheted bulk temperature and 2) a large increase in temperature of the mirror during the pulse. A new design was proposed and implemented which has extended the capability of the mirror to 10 s with passive cooling. The important features of the new design are 1) increase in the passive heat transfer rate during cooling and 2) a modified shape of the mirror. The analysis shows that, the new mirrors can be used for 10 s pulses. The new mirrors have been installed in DIII-D, they have been used for up to 2 s pulses.","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":"81076463","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.2002.1027709
C. Portafaix, B. Bertrand, P. Chappuis, J. Cordier, F. Faisse, P. Garin, P. Hertout, G. Martin, R. Mitteau, E. Thomas, E. Tsitrone
After a one year shutdown devoted to the installation of Tore Supra new components (CIEL project) and the associated diagnostics, the first experimental campaign is mainly dedicated to the qualification of these high heat flux components and the general commissioning of the machine. Because of the delay of delivery of the high flux components (so-called fingers) and in order to enable the qualification of CIEL main components, a start version of the Tore Supra/CIEL Toroidal Pump Limiter (TPL) has been designed and manufactured.
{"title":"Design and manufacture of the Toroidal Pump Limiter-start up version for the CIEL project","authors":"C. Portafaix, B. Bertrand, P. Chappuis, J. Cordier, F. Faisse, P. Garin, P. Hertout, G. Martin, R. Mitteau, E. Thomas, E. Tsitrone","doi":"10.1109/FUSION.2002.1027709","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027709","url":null,"abstract":"After a one year shutdown devoted to the installation of Tore Supra new components (CIEL project) and the associated diagnostics, the first experimental campaign is mainly dedicated to the qualification of these high heat flux components and the general commissioning of the machine. Because of the delay of delivery of the high flux components (so-called fingers) and in order to enable the qualification of CIEL main components, a start version of the Tore Supra/CIEL Toroidal Pump Limiter (TPL) has been designed and manufactured.","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":"https://sci-hub-pdf.com/10.1109/FUSION.2002.1027709","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72525061","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.2002.1027638
G. Cambi, D. Cepraga, M. Frisoni, L. Manzana, F. Carloni, M. L. Fiandri
To demonstrate fusion's environmental attractiveness over the entire life cycle, a waste analysis is mandatory. The clearance is recommended by IAEA for releasing activated solid materials from regulatory control and for waste management policy. The paper focus on the approach used to support waste analyses for ITER Generic Site Safety Report. The Material Unconditional Clearance Index of all the materials/zones on the equatorial mid-plane of ITER machine have been evaluated, based on IAEA-TECDOC-855. The Bonami-Nitawl-XSDNRPM sequence of the Scale-4.4a code system (using Vitenea-J library) has been firstly used for radiation transport analyses. Then the Anita-2000 code package is used for the activation calculation. The paper presents also, as an example, an application of the clearance indexes estimation for the ITER vacuum vessel materials. The results of the Anita-2000 have been compared with those obtained using the Fispact-99 activation code.
{"title":"Anita-2000 activation code package: clearance assessment of ITER activated materials","authors":"G. Cambi, D. Cepraga, M. Frisoni, L. Manzana, F. Carloni, M. L. Fiandri","doi":"10.1109/FUSION.2002.1027638","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027638","url":null,"abstract":"To demonstrate fusion's environmental attractiveness over the entire life cycle, a waste analysis is mandatory. The clearance is recommended by IAEA for releasing activated solid materials from regulatory control and for waste management policy. The paper focus on the approach used to support waste analyses for ITER Generic Site Safety Report. The Material Unconditional Clearance Index of all the materials/zones on the equatorial mid-plane of ITER machine have been evaluated, based on IAEA-TECDOC-855. The Bonami-Nitawl-XSDNRPM sequence of the Scale-4.4a code system (using Vitenea-J library) has been firstly used for radiation transport analyses. Then the Anita-2000 code package is used for the activation calculation. The paper presents also, as an example, an application of the clearance indexes estimation for the ITER vacuum vessel materials. The results of the Anita-2000 have been compared with those obtained using the Fispact-99 activation code.","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":"80959570","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.2002.1027641
D. Ćirić, J. Milnes, E. Surrey
Accurate accelerator grid alignment is a major factor governing the properties of multi-aperture particle beams. It is particularly important for JET positive ion neutral injectors (PINIs), where accelerators are constructed of two grid halves. Grid misalignment can lead to increased power loading of beam intercepting components, to reduced beam transmission, and, finally, to reduced neutral beam power injected into plasma. A new PINI accelerator assembly procedure, which utilises a robotic arm measuring device, was recently developed at JET. PINI alignment data are used as input to a beam simulation code to predict beam properties prior to testing at the Neutral Beam Test Bed. Since the new PINI assembly procedure and the associated computer code have been implemented the alignment of JET PINIs has been considerably improved.
{"title":"Influence of accelerator grid misalignment on multi-aperture particle beam properties","authors":"D. Ćirić, J. Milnes, E. Surrey","doi":"10.1109/FUSION.2002.1027641","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027641","url":null,"abstract":"Accurate accelerator grid alignment is a major factor governing the properties of multi-aperture particle beams. It is particularly important for JET positive ion neutral injectors (PINIs), where accelerators are constructed of two grid halves. Grid misalignment can lead to increased power loading of beam intercepting components, to reduced beam transmission, and, finally, to reduced neutral beam power injected into plasma. A new PINI accelerator assembly procedure, which utilises a robotic arm measuring device, was recently developed at JET. PINI alignment data are used as input to a beam simulation code to predict beam properties prior to testing at the Neutral Beam Test Bed. Since the new PINI assembly procedure and the associated computer code have been implemented the alignment of JET PINIs has been considerably improved.","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":"74432537","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.2002.1027684
P. Roney, K. Tindall, S. Davis
The National Spherical Torus Experiment (NSTX) began acquiring data in February 1999. From the beginning it utilized a heterogeneous collection of computer platforms for control, data acquisition, analysis and. security. Computer processing, data acquisition and storage, and network capacity have been subsequently increased. The variety of platforms used for data acquisition and analysis, as well as the number of protocols used on the Ethernet, have also increased. Network capacity has been added to support a growing load of Ethernet-based data acquisition hardware, to handle increased firewall traffic, and to provide bandwidth for visualization of analysis results. Networked video provides broadcast views of the control room and meetings. Four-party video conferencing in the control room allows communication among the members of the national team.
{"title":"Computer and network infrastructure of the National Spherical Torus Experiment","authors":"P. Roney, K. Tindall, S. Davis","doi":"10.1109/FUSION.2002.1027684","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027684","url":null,"abstract":"The National Spherical Torus Experiment (NSTX) began acquiring data in February 1999. From the beginning it utilized a heterogeneous collection of computer platforms for control, data acquisition, analysis and. security. Computer processing, data acquisition and storage, and network capacity have been subsequently increased. The variety of platforms used for data acquisition and analysis, as well as the number of protocols used on the Ethernet, have also increased. Network capacity has been added to support a growing load of Ethernet-based data acquisition hardware, to handle increased firewall traffic, and to provide bandwidth for visualization of analysis results. Networked video provides broadcast views of the control room and meetings. Four-party video conferencing in the control room allows communication among the members of the national team.","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":"77768970","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.2002.1027738
C. Skinner, C. Gentile, A. Hassanein
A new technique for studying high heat flux interactions with plasma facing components is presented. The beam from a continuous wave 300 W neodymium laser was focussed to 80 W/mm/sup 2/ and scanned at high speed over the surface of carbon tiles. These tiles were previously used in the TFTR inner limiter and have a surface layer of amorphous hydrogenated carbon that was codeposited during plasma operations. Laser scanning released up to 84% of the codeposited tritium. The temperature rise of the codeposit on the tiles was significantly higher than that of the manufactured material. In one experiment, the codeposit surface temperature rose to 1,770/spl deg/C while for the same conditions, the manufactured surface increased to only 1,080/spl deg/C. The peak temperature did not follow the usual square-root dependence on heat pulse duration.
{"title":"High heat flux interactions and tritium removal from plasma facing components by a scanning laser","authors":"C. Skinner, C. Gentile, A. Hassanein","doi":"10.1109/FUSION.2002.1027738","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027738","url":null,"abstract":"A new technique for studying high heat flux interactions with plasma facing components is presented. The beam from a continuous wave 300 W neodymium laser was focussed to 80 W/mm/sup 2/ and scanned at high speed over the surface of carbon tiles. These tiles were previously used in the TFTR inner limiter and have a surface layer of amorphous hydrogenated carbon that was codeposited during plasma operations. Laser scanning released up to 84% of the codeposited tritium. The temperature rise of the codeposit on the tiles was significantly higher than that of the manufactured material. In one experiment, the codeposit surface temperature rose to 1,770/spl deg/C while for the same conditions, the manufactured surface increased to only 1,080/spl deg/C. The peak temperature did not follow the usual square-root dependence on heat pulse duration.","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":"88874409","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.2002.1027737
P. Chaudhuri, D. C. Reddy, S. Khirwadkar, N. R. Prakash, P. Santra, Y. Saxena
Steady state Superconducting Tokamak (SST-1) to address some of the physics and technology issues related to steady state tokamak operation. The plasma facing components (PFC) of SST-1, placed inside the vacuum vessel (VV) of the tokamak, are designed to be compatible for steady state operation. The main consideration in the design of the PFC is the steady state heat removal of up to 1 MW/m/sup 2/. In addition to remove high heat fluxes, the PFC also arc designed to be compatible for high temperature baking. The thermal responses of the PFC and VV during their bakeout phase have been calculated analytically and with a 2D finite element analysis using ANSYS. The detailed analysis of radiation losses between the PFC and VV and the thermal-hydraulics of PFC baking are presented.
{"title":"Thermal response and thermal-hydraulic analysis of PFC baking for SST-1 tokamak","authors":"P. Chaudhuri, D. C. Reddy, S. Khirwadkar, N. R. Prakash, P. Santra, Y. Saxena","doi":"10.1109/FUSION.2002.1027737","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027737","url":null,"abstract":"Steady state Superconducting Tokamak (SST-1) to address some of the physics and technology issues related to steady state tokamak operation. The plasma facing components (PFC) of SST-1, placed inside the vacuum vessel (VV) of the tokamak, are designed to be compatible for steady state operation. The main consideration in the design of the PFC is the steady state heat removal of up to 1 MW/m/sup 2/. In addition to remove high heat fluxes, the PFC also arc designed to be compatible for high temperature baking. The thermal responses of the PFC and VV during their bakeout phase have been calculated analytically and with a 2D finite element analysis using ANSYS. The detailed analysis of radiation losses between the PFC and VV and the thermal-hydraulics of PFC baking are presented.","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":"82204462","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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