Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027712
T. Shibata, T. Akiyama, N. Isei, H. Kawashima, H. Kimura, K. Miyachi, F. Okano, M. Sato, S. Suzuki, K. Tsuzuki, M. Yamamoto
On JFT-2M, to investigate whether low-activation ferritic steel (F82H) can be used as a structural material of the demonstration reactor, the Advanced Material Tokamak EXperiment (AMTEX) is being carried out step by step. The AMTEX program consists of three stages. In the 1st stage, the low-activation ferritic steel plates (FPs) were inserted between the vacuum vessel (VV) and the toroidal field coils (TFCs) to reduce the toroidal field ripple. In the 2nd stage, the pre-testing of compatibility with plasma was carried out by partially installing the FPs in the inside of VV. In the 3rd (final) stage, the testing of compatibility with plasma will be carried out by a full covering of the FPs on the inside of VV.
{"title":"Advanced Material Tokamak EXperiment (AMTEX) on JFT-2M - design, fabrication, installation and conditioning of inside ferritic steel wall","authors":"T. Shibata, T. Akiyama, N. Isei, H. Kawashima, H. Kimura, K. Miyachi, F. Okano, M. Sato, S. Suzuki, K. Tsuzuki, M. Yamamoto","doi":"10.1109/FUSION.2002.1027712","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027712","url":null,"abstract":"On JFT-2M, to investigate whether low-activation ferritic steel (F82H) can be used as a structural material of the demonstration reactor, the Advanced Material Tokamak EXperiment (AMTEX) is being carried out step by step. The AMTEX program consists of three stages. In the 1st stage, the low-activation ferritic steel plates (FPs) were inserted between the vacuum vessel (VV) and the toroidal field coils (TFCs) to reduce the toroidal field ripple. In the 2nd stage, the pre-testing of compatibility with plasma was carried out by partially installing the FPs in the inside of VV. In the 3rd (final) stage, the testing of compatibility with plasma will be carried out by a full covering of the FPs on the inside of VV.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"26 1","pages":"360-363"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73057066","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027689
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":"21 1","pages":"256-259"},"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":"16 1","pages":"137-139"},"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.2002.1027650
Y. Srinivas, M. Kushwah, S. Kulkarni, K. Sathyanarayana, P. Khilar, B. Pal, P. Shah, A. Makwana, B. Kadia, K. Parmar, S. Dani, R. Singh, K. Parmar, D. Bora
Pulsed and continuous high power microwave tubes need to be protected against arc faults within the tube. If the energy dumped in such arc fault is more than the critical crater energy of the tube, irreparable damage can occur. Modern switch mode powers supplies (SMPS) that are generally opted for the new systems store little energy and are capable of switching HV in few microseconds. So they do not need separate protection. However, when conventional power supplies feed high power microwave tubes a reliable crowbar protection system, tested separately to limit the energy, must be used to assure the tube safety. Initial testing and commissioning of two klystrons, TH2103D have been carried out at our Institute. Each of these klystrons is capable of delivering 500 kW at 3.7 GHz, to be used for non-inductive lower hybrid current drive (LHCD) In the Steady-State Superconducting Tokamak-1 (SST-1). Commissioning of the gyrotron VGA8000A19, for breakdown and electron cyclotron resonant heating (ECRH) experiments on Aditya tokamak, has also been carried out.
{"title":"Results of 10-Joule wire-burn test performed on 70 kV rail-gap crowbar protection system for high power klystrons and gyrotron","authors":"Y. Srinivas, M. Kushwah, S. Kulkarni, K. Sathyanarayana, P. Khilar, B. Pal, P. Shah, A. Makwana, B. Kadia, K. Parmar, S. Dani, R. Singh, K. Parmar, D. Bora","doi":"10.1109/FUSION.2002.1027650","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027650","url":null,"abstract":"Pulsed and continuous high power microwave tubes need to be protected against arc faults within the tube. If the energy dumped in such arc fault is more than the critical crater energy of the tube, irreparable damage can occur. Modern switch mode powers supplies (SMPS) that are generally opted for the new systems store little energy and are capable of switching HV in few microseconds. So they do not need separate protection. However, when conventional power supplies feed high power microwave tubes a reliable crowbar protection system, tested separately to limit the energy, must be used to assure the tube safety. Initial testing and commissioning of two klystrons, TH2103D have been carried out at our Institute. Each of these klystrons is capable of delivering 500 kW at 3.7 GHz, to be used for non-inductive lower hybrid current drive (LHCD) In the Steady-State Superconducting Tokamak-1 (SST-1). Commissioning of the gyrotron VGA8000A19, for breakdown and electron cyclotron resonant heating (ECRH) experiments on Aditya tokamak, has also been carried out.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"2 1","pages":"91-94"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81233040","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"艺术学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2002-11-07DOI: 10.1109/FUSION.2002.1027641
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":"195 1","pages":"56-59"},"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.2002.1027709
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":"47 1","pages":"348-351"},"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":"24 1","pages":"44-47"},"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.2002.1027676
P. Titus
The baseline toroidal field coil system of the FIRE tokamak utilizes inertially cooled, copper alloy Bitter plate type magnets which are LN/sub 2/ cooled between shots. The TF configuration is wedged and uses C17510 high strength, high conductivity beryllium copper alloy which was developed for BPX in the inner leg, where the stress is highest. In FY 01, a slightly larger design was adopted (R=2.14 m. compared to the previous 2.0 m.)which affords better physics performance with lower TF field, and thus lower TF stresses. Bucked and wedged (B&W) TF designs have also been considered. The B&W design results in lower coil stresses in the inner leg that may be used to increase field or design margin, or alternatively could allow the use of high conductivity OFHC copper which would allow longer pulse lengths. B&W designs require good fit-up, and effects of fit-up uncertainties, friction factor variations, and methods of evaluating primary load paths are presented. The effects of the size change and possible changes in structural concept are summarized.
{"title":"Alternative structural concepts for the Fusion Ignition Research Experiment (FIRE)","authors":"P. Titus","doi":"10.1109/FUSION.2002.1027676","DOIUrl":"https://doi.org/10.1109/FUSION.2002.1027676","url":null,"abstract":"The baseline toroidal field coil system of the FIRE tokamak utilizes inertially cooled, copper alloy Bitter plate type magnets which are LN/sub 2/ cooled between shots. The TF configuration is wedged and uses C17510 high strength, high conductivity beryllium copper alloy which was developed for BPX in the inner leg, where the stress is highest. In FY 01, a slightly larger design was adopted (R=2.14 m. compared to the previous 2.0 m.)which affords better physics performance with lower TF field, and thus lower TF stresses. Bucked and wedged (B&W) TF designs have also been considered. The B&W design results in lower coil stresses in the inner leg that may be used to increase field or design margin, or alternatively could allow the use of high conductivity OFHC copper which would allow longer pulse lengths. B&W designs require good fit-up, and effects of fit-up uncertainties, friction factor variations, and methods of evaluating primary load paths are presented. The effects of the size change and possible changes in structural concept are summarized.","PeriodicalId":44192,"journal":{"name":"NINETEENTH CENTURY MUSIC","volume":"159 1","pages":"200-204"},"PeriodicalIF":0.4,"publicationDate":"2002-11-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79535195","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":"46 1","pages":"469-472"},"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}
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":"9 1","pages":"473-476"},"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}
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