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Some years ago, it was operated and controlled on a 486 PC with Microsoft Windows 3.1. A 16-bit software package called FIXDMACS was used to interface and communicate with Siemens programmable logic controllers (PLCs). Due to the ever-changing operation requirements, this system became antiquated and failed to adequately support new process conditions and meet the NB operational demands. It was, therefore, inevitable that a system upgrade would be needed to satisfy efficiency and performance. This project required a comprehensive survey of available hardware and software currently offered by the leading industries. The best solution was a complete replacement of the entire workstation. A new Dell Pentium III PC, equipped with Windows NT, was acquired to replace the old SCADA system. FIXDMACS was replaced by scalable iFIX, which was also developed by Intellution. In addition, data migration and conversion was performed to enable forward compatibility of all existing software and system configurations. Besides delivering an excellent solution to monitoring the neutral beam system operations, iFIX is able to accept Microsoft Visual Basic scripts and programs to automate routine or repetitive tasks, allowing system administrators to execute these tasks and controls quickly. This added feature provides flexibility and simplicity for maintaining and troubleshooting purposes. Although additional improvements are always possible as with all other software products, iFIX has proven to be a valuable tool in supporting the operations. Packaged with essential enhancements, new capabilities and powerful tools, Intellution has developed an application that certainly surpasses its predecessor. Today, the upgraded DIII-D Neutral Beam SCADA system is fully operational. Both hardware and software upgrades were a cost effective and necessary approach toward achieving the goals of maximizing system performance, improving efficiency and reliability, and providing better control of the neutral beam operational processes.",{"EN":35},"The DIII-D Neutral Beam Supervisory Control and Data Acquisition workstation upgrade",{"VOID":37},"10.1109\u002FFUSION.2002.1027636","PUBLICATION","VERIFIED","Auto Verify","https:\u002F\u002Fieeexplore.ieee.org\u002Fabstract\u002Fdocument\u002F1027636\u002F","https:\u002F\u002Fieeexplore.ieee.org\u002Fstamp\u002Fstamp.jsp?tp=&arnumber=1027636",[44,67,82],{"id":45,"sortIndex":46,"researcher":9,"roles":47,"affiliations":49,"properties":64},"0e20bfd7-62b0-4910-8b86-a01fa668ba29",2,[48],"AUTHOR",[50],{"id":51,"sortIndex":15,"affiliation":52,"properties":61},"8a317146-6660-4bed-8b43-b0a6f655487d",{"id":53,"createTime":54,"updateTime":54,"relativeEntities":55,"slug":56,"properties":57,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},"e8a745b3-39f8-4924-ab3d-be9127745272","2024-10-14T11:15:51.063+00:00",[],"General-Atomics-San-Diego-CA-United-States-",{"title":58},{"EN":59},"General Atomics, San Diego, CA (United States)","AFFILIATION",{"title":62},{"VI":63},"General Atomics, San Diego, CA, USA",{"title":65},{"VI":66},"D.H. 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Busath","ARTICLE",{"url":41,"publisher":100,"properties":107},{"id":6,"createTime":7,"updateTime":7,"relativeEntities":101,"slug":9,"properties":102,"entityType":13,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15,"subjectFields":104,"manageAffiliations":105,"indexDatabases":106,"url":9,"thumbnailPath":9,"statistic":9,"gsStatistic":9,"type":9,"analyzePriority":9},[],{"title":103},{"EN":12},[],[],[],{"pages":108},{"VOID":109},"36-39",false,{"id":112,"createTime":113,"updateTime":114,"relativeEntities":115,"slug":116,"properties":117,"entityType":38,"verifyStatus":39,"verifyTime":114,"verifyNote":40,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15,"primaryUrl":128,"fullTextUrl":129,"authors":130,"publicationType":98,"publisherRelationship":209,"citationCount":9,"citationInfo":9,"publishDate":9,"publishYear":9,"citationAnalyzeStatus":14,"lastCitationAnalyze":9,"indexDatabases":9,"openAccess":9,"references":9,"isForceReanalyzing":110},"58b7cc6a-b5d4-46ac-a21f-410143a95917","2023-12-22T12:01:49.681+00:00","2025-01-25T23:46:48.120+00:00",[],"Compact-probe-design-for-power-monitoring-from-the-narrow-side-of-the-reduced-height-waveguide",{"references":118,"keywords":120,"abstract":122,"title":124,"doi":126},{"VOID":119},"ramo, 1994, Fields and Wave in Communication Eectronics, 417\n10.1063\u002F1.1147880\nmatthaei, 1980, Microwave Filters, Impedance-Matching Networks, and Coupling Structures\nbalanis, 1982, Antenna Theory. Analysis and Design, 169\nbibet, 1990, Scattering Matrix of Tore Supra Lower Hybrid Antenna, Associatiion Euratom-C E A EUR-CEA-FC-1390\n10.1088\u002F0029-5515\u002F28\u002F2\u002F004",{"EN":121},"Probes,Monitoring,Directional couplers,Impedance,Power transmission lines,Plasma confinement,Capacitors,Testing,Tokamaks,Power cables",{"EN":123},"Due to confined space in a stack of reduced height waveguides, power detection of the incident and reflected wave in the reduced height waveguide is extremely difficult. A new compact probe to monitor the incident and reflected wave from the narrow side of the reduced height waveguide has been developed. This compact probe consists of 2 current loops, a directional coupler, and a small trimmer capacitor. The two current loops are placed on the narrow side of the waveguide with a quarter guide wavelength (\u002Fspl lambda\u002F\u002Fsub g\u002F\u002F4) spacing. The outputs of the current loops are connected to the directional coupler. In order to optimize phase adjustment, a trimmer capacitor is attached in series with one of the current loops. Test results show that more than 30 dB directivity at 4.6 GHz is achieved by using this compact probe.",{"EN":125},"Compact probe design for power monitoring from the narrow side of the reduced height waveguide",{"VOID":127},"10.1109\u002FFUSION.2002.1027692","https:\u002F\u002Fieeexplore.ieee.org\u002Fabstract\u002Fdocument\u002F1027692\u002F","https:\u002F\u002Fieeexplore.ieee.org\u002Fstamp\u002Fstamp.jsp?tp=&arnumber=1027692",[131,147,169,181,194],{"id":132,"sortIndex":133,"researcher":9,"roles":134,"affiliations":135,"properties":144},"e380d9b0-ed89-48a8-bd31-86ee3866e895",3,[48],[136],{"id":9,"sortIndex":15,"affiliation":137,"properties":9},{"id":138,"createTime":139,"updateTime":139,"relativeEntities":140,"slug":9,"properties":141,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},"bda05545-b550-4a67-94b4-ae2563b6bbee","2023-12-22T12:01:49.697+00:00",[],{"title":142},{"VI":143},"Princeton Plasma Physics Laboratory, Princeton, New Jersey, USA",{"title":145},{"VI":146},"N. 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0, this proceedings\ndavis, 1999, J Nucl Mat, 478, 266\nwang, 1989, J Nucl Mat, 422, 162\nfederici, 1997, J Nucl Mat, 260, 241\nwinter, 1999, J Nucl Mat, 228, 266\n10.1097\u002F00004032-199902000-00003\ncarmack, 2000, Fus Eng Des, 477, 51\n10.1103\u002FRevModPhys.70.537\n10.1088\u002F0741-3335\u002F40\u002F6\u002F022\nroth, 2001, Phys Scripta T, 65\n10.1088\u002F0029-5515\u002F41\u002F8\u002F312\ncheng, 2001, Characterization of carbon tritide particles in a tokamak fusion reactor, 6th Int Conf on Tritium Science and Technol\nbarabash, 2000, J Nucl Mat, 1248, 283\nschlosser, 1998, Fus Eng Des, 235, 39\nbarabash, 1998, Joining technologies for the plasma-facing components of IT?R, Proc 20'* Symp Fus Technol, 1, 215\n10.1016\u002FS0920-3796(99)00053-8\neckstein, 0, Particle induced Erosion of Be, C and fP in Fusion Plasmas, Pari B physical Sputtering and Radiation Enhanced Sublimation in Atomic and Plasma-Material Interaction Data for Fusion, 7b\nbarabash, 2000, J Nucl Mat, 1248, 283\nmerola, 2000, J Nucl Mat, 106, 283\n10.1016\u002FS0920-3796(99)00048-4\nhassanein, 0, J Nucl Mat\nfederici, 2001, J Nucl Mat, 260, 290\n10.1088\u002F0029-5515\u002F38\u002F12\u002F305\n10.1016\u002FS0920-3796(89)80007-9\n10.1088\u002F0029-5515\u002F40\u002F6\u002F316\n10.1016\u002F0920-3796(94)90017-5\nparker, 1997, J Nucl Mat, 1, 241\n10.1016\u002F0022-3115(93)90025-T\nbartels, 1992, Runaway electrons on PFC, Proc 17th Symp Fus Technol, 1, 181\nmeade, 2000, Proc IS* Int Conf Sorrento\n10.1016\u002FS0022-3115(98)00876-9\n10.1238\u002FPhysica.Topical.091a00076\nlonghurst, 1995, Fus Technol 2, 1217, 10.13182\u002FFST95-A30575\n10.1238\u002FPhysica.Topical.081a00074\n10.1088\u002F0029-5515\u002F41\u002F12\u002F218\n10.1088\u002F0029-5515\u002F37\u002F3\u002FI12\nwhyte, 1997, J Nucl Mat, 660, 241\n10.1016\u002F0022-3115(94)00406-4\nshimizu, 1997, J Nucl Mat, 167, 241\nguo, 1997, J Nucl Mat, 385, 241\npappas, 1999, Nucl Mater, 635, 266\nwampler, 1999, J Nucl Mat, 217, 266\n10.1088\u002F0029-5515\u002F41\u002F9\u002F313\nbrooks, 1983, Nucl Technol Fusion, 4, 33, 10.13182\u002FFST83-A22772\nwuerz, 1998, A consistent 2D analysis of the ITER 2D divertor, Proc 20th Symp Fus Technol Marseille France, 1, 271\nhill, 1997, J Nucl Mat, 182, 241\n10.1016\u002FS0022-3115(98)00522-4\n1999, ITER Physics Basis, Nucl Fusion, 39, 2137\nloarte, 0, Proc I801 Int Conf Sorrento 2000 IAEA Vienna (2001) IAEA-CN-77 CD-ROM file ITERIVI 1(R)\n10.1088\u002F0741-3335\u002F38\u002F2\u002F001\ncoster, 1997, J Nucl Mat, 690, 241\n10.1063\u002F1.859457\n10.1088\u002F0029-5515\u002F36\u002F12\u002FI05\nroth, 1982, J Nucl Mat, 775, 111\n10.1063\u002F1.872854\nphilipps, 1982, J Nucl Mat, 781, 111\n10.1016\u002F0008-6223(95)00171-9\nthomas, 1990, J Nucl Mat, 3, 176\n10.1088\u002F0029-5515\u002F26\u002F9\u002F004\npiet, 1997, ITER tokamak dust-Iimits. production, removal, surveying, Ptoc 17th IEEE\u002FNPSS Symp Fus Eng, 1, 167, 10.1109\u002FFUSION.1997.687012\nhackmatm, 1984, J Nucl Mat, 418, 128\npetti, 1996, J Nucl Mat, 37, 233\n10.1063\u002F1.870701\nrazdobarin, 0, Detecting dust on plasma-facing components in a next-step tokamak using a laser induced breakdown spectroscopy technique, Fus Sci Technol\nkrieger, 1999, the ASDEX Upgrade Team 1 Nucl Mat, 207, 266\ncounsell, 2001, J Phys Scripta, 70\nneu, 2001, J Nucl Mat, 206, 290\npetti, 1998, Technol, 34, 390\n10.1109\u002FFUSION.2002.1027629\nbolt, 2001, Plasma-facing and high-heat flux materials – needs for ITER and beyond, 10th Int Conf on Fus React Mat\n10.1088\u002F0741-3335\u002F41\u002F12B\u002F318\n10.1088\u002F0029-5515\u002F19\u002F7\u002F004\ncounsell, 2001, J Nucl Mat, 255, 290\neubank, 1979, PLT neutral beam heating results, Proc 7th Conf on Plasma Phys Contr Nucl Fus Res held by the IAEA in Innsbruck (Austria) 1978 IAEA, 1, 167\ncoad, 2001, J Nucl Mat, 225, 290\nmeservey, 1980, J Nucl Mat, 267, 93\ndavis, 1997, J Nucl Mat, 37, 241\nbooks, 0, Personal communication\nvietzke, 1996, Physical Processes of the Interaction of Fusion Plasmas with Solids, 135\n10.1088\u002F0029-5515\u002F37\u002F7\u002FI04\n10.1063\u002F1.873445\nroth, 1999, J Nucl Mat, 51, 266\n10.1002\u002Fctpp.2150380103\n10.1109\u002FFUSION.1999.849834\n10.1088\u002F0029-5515\u002F39\u002F8\u002F306\npautasso, 2001, J Nucl Mat, 1045, 290\n10.1016\u002FS0022-3115(99)00022-7",{"EN":230},"Plasma devices,Plasma materials processing,Fusion reactor design,Plasma applications,Robustness,Solids,Fusion reactors,Research and development,Design engineering,Power engineering and energy",{"EN":232},"Designing a robust interface between a thermonuclear plasma and the solid material environment remains a major challenge for next-step fusion devices and future power fusion reactors. Challenging trade-offs in material choice for plasma-facing components were identified in the internationally co-ordinated R&D program supporting the Engineering Design Activities of the ITER project. This paper surveys factors relevant to material choices in next-step devices, describes advantages and disadvantages of the various options, and discusses how their application depends on the specific operational requirements. Advances in materials technology with high-Z materials, together with improved plasma control leading to reduction and mitigation of off-normal events such as disruptions and ELMs, are an essential part of the long-term solution.",{"EN":234},"Selection of plasma-facing materials in next-step fusion devices",{"VOID":236},"10.1109\u002FFUSION.2002.1027701","2025-01-05T23:41:03.089+00:00","Author affiliation is blank","https:\u002F\u002Fieeexplore.ieee.org\u002Fabstract\u002Fdocument\u002F1027701\u002F","https:\u002F\u002Fieeexplore.ieee.org\u002Fstamp\u002Fstamp.jsp?tp=&arnumber=1027701",[242,257,273,290,298,314,326,338],{"id":243,"sortIndex":133,"researcher":9,"roles":244,"affiliations":245,"properties":254},"b279794d-81c5-4383-b006-8ae482d0d972",[48],[246],{"id":9,"sortIndex":15,"affiliation":247,"properties":9},{"id":248,"createTime":249,"updateTime":249,"relativeEntities":250,"slug":9,"properties":251,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},"43aa5473-0a78-42c8-b7b5-5ea94df02451","2023-12-22T12:20:17.741+00:00",[],{"title":252},{"VI":253},"ITER-CTA International Team, Garching, Germany",{"title":255},{"VI":256},"R. 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The engineering and technology development activities arc closely aligned with the major experimental areas, which include injectors, beam transport, and final focus. High current density ion sources to produce a more compact multiple beam injector are a major focus of the current activities. There are several collaborations with insulator manufacturers to achieve higher gradients while lowering the manufacturing cost and maintaining high vacuum compatibility. Solid-state pulser technology is being pursued through an SBIR contract to provide reliable pulsers with agile waveform control, a required capability to compress the beam and correct for space charge effects. Ferromagnetic material development is continuing to look at low-loss, high flux swing material that is affordable. The testing of prototype pulsed and superconducting magnets over the last year has provided the basis for developing both of these magnet systems for the present single beam experiments. A heavy ion fusion driver will require continued technology development in these areas to meet the required performance goals and remain economically feasible.",{"EN":375},"Engineering and enabling technology development for heavy ion fusion drivers",{"VOID":377},"10.1109\u002FFUSION.2002.1027740","2024-12-15T23:37:07.587+00:00","https:\u002F\u002Fieeexplore.ieee.org\u002Fabstract\u002Fdocument\u002F1027740\u002F","https:\u002F\u002Fieeexplore.ieee.org\u002Fstamp\u002Fstamp.jsp?tp=&arnumber=1027740",[382,401,416,433],{"id":383,"sortIndex":133,"researcher":9,"roles":384,"affiliations":385,"properties":398},"a8c7d295-2773-4ee7-8325-0e3846811b1e",[48],[386],{"id":387,"sortIndex":15,"affiliation":388,"properties":395},"5a8a1221-a2d3-4916-afe5-32007f257e8e",{"id":389,"createTime":390,"updateTime":390,"relativeEntities":391,"slug":9,"properties":392,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},"107af14a-48ae-4554-b730-2e9af10dc9e6","2023-12-14T02:40:59.936+00:00",[],{"title":393},{"VI":394},"Lawrence Berkeley National Laboratory, Berkeley, CA, United States",{"title":396},{"VI":397},"Lawrence Berkeley National Laboratory, Berkeley, CA, USA",{"title":399},{"VI":400},"G. 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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.",{"EN":475},"Post-test calculations with ISAS-ITER system for ICE experiments",{"VOID":477},"10.1109\u002FFUSION.2002.1027639","https:\u002F\u002Fieeexplore.ieee.org\u002Fabstract\u002Fdocument\u002F1027639\u002F","https:\u002F\u002Fieeexplore.ieee.org\u002Fstamp\u002Fstamp.jsp?tp=&arnumber=1027639",[481,496],{"id":482,"sortIndex":84,"researcher":9,"roles":483,"affiliations":484,"properties":493},"e526fc8a-3bd7-4ab8-b782-bae86e28d60a",[48],[485],{"id":9,"sortIndex":15,"affiliation":486,"properties":9},{"id":487,"createTime":488,"updateTime":488,"relativeEntities":489,"slug":9,"properties":490,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},"d4156ada-5465-4683-9514-12d1f1ad26d6","2023-12-21T05:44:16.882+00:00",[],{"title":491},{"VI":492},"ENEA SIEC, Bologna, Italy",{"title":494},{"VI":495},"P. 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According to the requirement of the physics design, sixteen horizontal ports on outboard mid-plane and thirty-two vertical ports on the top and bottom are designed for diagnostics, plasma heating, current driving, vacuum pumping and gas puffing. Bellows on these ports are used for flexible components to absorb the relative displacement in radial and vertical directions due to the external load, thermal expansion or contraction, assembly toleration and as well as for isolation of mechanical vibration. Some three-dimension finite element COSMOS models were performed to analysis its structural strength, stiffness and fatigue life, laying the emphasis on these bellows static stress analysis. The load case spectra during vacuum vessel operation were also simulated on a model from the view of fatigue design. It was confirmed that these bellows have sufficient strength in range of the design load conditions. The results showed the bellows peak stress was 87 MPa and its fatigue cumulative usage factor was only 0.01, which was less than critical value of 1. Now all kinds of bellows have been designed. In order to accumulate some engineering experiences and probe into some molding die and welding technologies, a prototypical bellows have been fabricated. At the same time a mechanical testing apparatus was designed for proof tests on the prototypical bellows to verify its functional and structure capability. The experimental data indicated that the results of finite element analysis were coincident with experimental test results. It has been proved that the present vacuum vessel's bellows are reasonable and feasible.",{"EN":536},"Structure analysis and experiment research of the welded bellows for the ports of the HT-7U vacuum 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Majeski",{"url":675,"publisher":1122,"properties":1129},{"id":6,"createTime":7,"updateTime":7,"relativeEntities":1123,"slug":9,"properties":1124,"entityType":13,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15,"subjectFields":1126,"manageAffiliations":1127,"indexDatabases":1128,"url":9,"thumbnailPath":9,"statistic":9,"gsStatistic":9,"type":9,"analyzePriority":9},[],{"title":1125},{"EN":12},[],[],[],{"pages":1130},{"VOID":1131},"341-344",{"id":1133,"createTime":1134,"updateTime":1135,"relativeEntities":1136,"slug":1137,"properties":1138,"entityType":38,"verifyStatus":39,"verifyTime":1135,"verifyNote":40,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15,"primaryUrl":1149,"fullTextUrl":1150,"authors":1151,"publicationType":98,"publisherRelationship":1199,"citationCount":9,"citationInfo":9,"publishDate":9,"publishYear":9,"citationAnalyzeStatus":14,"lastCitationAnalyze":9,"indexDatabases":9,"openAccess":9,"references":9,"isForceReanalyzing":110},"3cd9367c-b563-4375-a0e4-c573448048ec","2023-12-22T12:28:30.817+00:00","2025-01-23T21:57:35.073+00:00",[],"High-heat-flux-interactions-and-tritium-removal-from-plasma-facing-components-by-a-scanning-laser",{"references":1139,"keywords":1141,"abstract":1143,"title":1145,"doi":1147},{"VOID":1140},"10.1016\u002FS0022-3115(06)80109-1\n10.1016\u002FS0022-3115(00)00663-2\n10.1016\u002FS0022-3115(01)00679-1\n10.1016\u002FS0022-3115(98)00586-8\neckstein, 1996, Physical Sputtering and Radiation-Enhanced Sublimation, Physical Processes of the Interaction of Fusion Plasmas with Solids, 93\ncarslaw, 1959, Conduction of Heat in Solids, 75\n0, CRC Handbook of Chemistry and Physics\nbrooks, 1992, FDR report\n10.1016\u002F0022-3115(89)90292-4\nsmolik, 1990, Evaluation of graphite\u002Fsteam interactions for ITER, Idaho National Laboratory report\n10.1016\u002FS0022-3115(98)00586-8\n10.1007\u002F978-1-4419-8696-2_51\n10.1016\u002FS0022-3115(01)00679-1\nskinner, 0, Long term tritium trapping in TFTR and JET, Proceedings of the 28th EPS Conference on Controlled Fusion and Plasma Physics\n10.1016\u002FS0022-3115(02)00713-4\nskinner, 1997, Tritium removal by CO, laser heating, Proc 17th IEEE\u002FNPSS Symp Fusion Eng San Diego CA, 1, 321, 10.1109\u002FFUSION.1997.687047\n10.1016\u002FS0022-3115(99)00052-5\nskinner, 0, Tritium removal by laser heating and its application to tokarnaks, Proceedings of the 6th International Conference on Tritium Science and Technology\n10.1088\u002F0029-5515\u002F41\u002F12\u002F218\n10.1016\u002F0022-3115(94)00619-9\n10.1109\u002FFUSION.2002.1027701\npaffett, 2002, Surface Characterization of TFTR First Wall Graphite tiles used during DT operations, Fusion Science and Technology, 10.13182\u002FFST02-A22722\n10.1016\u002F0022-3115(89)90394-2\nlinke, 1990, Disruption simulation experiments in electron and laser beam facilities, Fusion Technol, 428\nhassanein, 1999, Physics of collisionless scrape-off-layer plasma during normal and off-normal tokamak operating conditions, Argonne Natlonal Laboratory Report ANL\u002FFPP\u002FTM-296\n10.1016\u002FS0022-3115(96)00015-3\n10.1016\u002FS0022-3115(96)00213-9\n10.1088\u002F0029-5515\u002F31\u002F10\u002F001",{"EN":1142},"Plasma temperature,Tiles,Plasma waves,Manufacturing,Laser beams,Neodymium,Surface waves,Surface emitting lasers,Amorphous materials,Plasma materials processing",{"EN":1144},"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\u002Fmm\u002Fsup 2\u002F 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\u002Fspl deg\u002FC while for the same conditions, the manufactured surface increased to only 1,080\u002Fspl deg\u002FC. The peak temperature did not follow the usual square-root dependence on heat pulse duration.",{"EN":1146},"High heat flux interactions and tritium removal from plasma facing components by a scanning laser",{"VOID":1148},"10.1109\u002FFUSION.2002.1027738","https:\u002F\u002Fieeexplore.ieee.org\u002Fabstract\u002Fdocument\u002F1027738\u002F","https:\u002F\u002Fieeexplore.ieee.org\u002Fstamp\u002Fstamp.jsp?tp=&arnumber=1027738",[1152,1163,1187],{"id":1153,"sortIndex":15,"researcher":9,"roles":1154,"affiliations":1155,"properties":1161},"b152e597-4200-4704-980d-f0f9e2e9099b",[48],[1156],{"id":9,"sortIndex":15,"affiliation":1157,"properties":9},{"id":305,"createTime":306,"updateTime":306,"relativeEntities":1158,"slug":9,"properties":1159,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},[],{"title":1160},{"VI":310},{"title":1162},{"VI":313},{"id":1164,"sortIndex":46,"researcher":9,"roles":1165,"affiliations":1166,"properties":1184},"5c35c52f-1573-4036-ac67-c8b68ca72f4e",[48],[1167,1179],{"id":1168,"sortIndex":84,"affiliation":1169,"properties":1178},"cdfb1d14-ec38-4f4e-a623-0bb79f6f8260",{"id":1170,"createTime":1171,"updateTime":1172,"relativeEntities":1173,"slug":1174,"properties":1175,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},"482f76b7-7827-4446-b78a-e5abf4faa9ba","2023-12-27T11:04:55.260+00:00","2024-12-20T06:56:53.055+00:00",[],"Argonne-National-Laboratory-Argonne-IL-USA",{"title":1176},{"VI":1177},"Argonne National Laboratory, Argonne, IL, USA",{},{"id":9,"sortIndex":15,"affiliation":1180,"properties":9},{"id":305,"createTime":306,"updateTime":306,"relativeEntities":1181,"slug":9,"properties":1182,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},[],{"title":1183},{"VI":310},{"title":1185},{"VI":1186},"A. Hassanein",{"id":1188,"sortIndex":84,"researcher":9,"roles":1189,"affiliations":1190,"properties":1196},"fb2094c4-5514-4a01-bfcf-2a1a82c24b96",[48],[1191],{"id":9,"sortIndex":15,"affiliation":1192,"properties":9},{"id":305,"createTime":306,"updateTime":306,"relativeEntities":1193,"slug":9,"properties":1194,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},[],{"title":1195},{"VI":310},{"title":1197},{"VI":1198},"C.A. Gentile",{"url":1149,"publisher":1200,"properties":1207},{"id":6,"createTime":7,"updateTime":7,"relativeEntities":1201,"slug":9,"properties":1202,"entityType":13,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15,"subjectFields":1204,"manageAffiliations":1205,"indexDatabases":1206,"url":9,"thumbnailPath":9,"statistic":9,"gsStatistic":9,"type":9,"analyzePriority":9},[],{"title":1203},{"EN":12},[],[],[],{"pages":1208},{"VOID":1209},"473-476",{"id":1211,"createTime":1212,"updateTime":1213,"relativeEntities":1214,"slug":1215,"properties":1216,"entityType":38,"verifyStatus":39,"verifyTime":1213,"verifyNote":40,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15,"primaryUrl":1227,"fullTextUrl":1228,"authors":1229,"publicationType":98,"publisherRelationship":1305,"citationCount":9,"citationInfo":9,"publishDate":9,"publishYear":9,"citationAnalyzeStatus":14,"lastCitationAnalyze":9,"indexDatabases":9,"openAccess":9,"references":9,"isForceReanalyzing":110},"d8cfff60-b60f-4619-826f-8e312a9bb6ae","2023-12-22T12:28:23.677+00:00","2024-10-13T21:08:58.582+00:00",[],"Thermal-response-and-thermal-hydraulic-analysis-of-PFC-baking-for-SST-1-tokamak",{"references":1217,"keywords":1219,"abstract":1221,"title":1223,"doi":1225},{"VOID":1218},"10.1080\u002F10407789308902612\n10.1109\u002FFUSION.2002.1027727\n10.1016\u002FS0920-3796(01)00184-3\nincropera, 1996, Fundamentals ot Heat and Mass Transfer\nsiegel, 1983, Thermal Radiation Heat Transfer, 202\nredler, 0, TPX memo No TPX GA 0124 KR 95\n1995, Manual Ansys Inc\nchaudhuri, 0, Radiative heat loads on PFC and VV during baking of SST-1 Tokamak, Fusion Engineering and Design\nhoward, 0, Engineering Design Manual, i\n10.1088\u002F0029-5515\u002F40\u002F6\u002F305",{"EN":1220},"Tokamaks,Steady-state,Plasma temperature,High temperature superconductors,Superconducting coils,Nitrogen,Thermal loading,Impurities,Heat transfer,Physics",{"EN":1222},"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\u002Fm\u002Fsup 2\u002F. 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.",{"EN":1224},"Thermal response and thermal-hydraulic analysis of PFC baking for SST-1 tokamak",{"VOID":1226},"10.1109\u002FFUSION.2002.1027737","https:\u002F\u002Fieeexplore.ieee.org\u002Fabstract\u002Fdocument\u002F1027737\u002F","https:\u002F\u002Fieeexplore.ieee.org\u002Fstamp\u002Fstamp.jsp?tp=&arnumber=1027737",[1230,1245,1257,1269,1281,1293],{"id":1231,"sortIndex":84,"researcher":9,"roles":1232,"affiliations":1233,"properties":1242},"1781cb60-eb18-43c9-9631-46cb339a0665",[48],[1234],{"id":9,"sortIndex":15,"affiliation":1235,"properties":9},{"id":1236,"createTime":1237,"updateTime":1237,"relativeEntities":1238,"slug":9,"properties":1239,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},"d0ee510e-0c45-4b9e-a10f-324828cca0c3","2024-01-12T15:58:13.830+00:00",[],{"title":1240},{"VI":1241},"Institute for Plasma Research, Bhat, India",{"title":1243},{"VI":1244},"D.C. Reddy",{"id":1246,"sortIndex":133,"researcher":9,"roles":1247,"affiliations":1248,"properties":1254},"fdf5b1d7-5757-4616-9cd7-0be7a4b3c0be",[48],[1249],{"id":9,"sortIndex":15,"affiliation":1250,"properties":9},{"id":1236,"createTime":1237,"updateTime":1237,"relativeEntities":1251,"slug":9,"properties":1252,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},[],{"title":1253},{"VI":1241},{"title":1255},{"VI":1256},"N.R. Prakash",{"id":1258,"sortIndex":15,"researcher":9,"roles":1259,"affiliations":1260,"properties":1266},"cb7626de-ed9c-42a6-9920-2c2746858b45",[48],[1261],{"id":9,"sortIndex":15,"affiliation":1262,"properties":9},{"id":1236,"createTime":1237,"updateTime":1237,"relativeEntities":1263,"slug":9,"properties":1264,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},[],{"title":1265},{"VI":1241},{"title":1267},{"VI":1268},"P. Chaudhuri",{"id":1270,"sortIndex":46,"researcher":9,"roles":1271,"affiliations":1272,"properties":1278},"39801cba-fdd5-4f2b-bca0-8c5ec6614c8d",[48],[1273],{"id":9,"sortIndex":15,"affiliation":1274,"properties":9},{"id":1236,"createTime":1237,"updateTime":1237,"relativeEntities":1275,"slug":9,"properties":1276,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},[],{"title":1277},{"VI":1241},{"title":1279},{"VI":1280},"S. Khirwadkar",{"id":1282,"sortIndex":259,"researcher":9,"roles":1283,"affiliations":1284,"properties":1290},"068d5701-2374-4e41-8111-d93c832d0e01",[48],[1285],{"id":9,"sortIndex":15,"affiliation":1286,"properties":9},{"id":1236,"createTime":1237,"updateTime":1237,"relativeEntities":1287,"slug":9,"properties":1288,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},[],{"title":1289},{"VI":1241},{"title":1291},{"VI":1292},"Y.C. Saxena",{"id":1294,"sortIndex":183,"researcher":9,"roles":1295,"affiliations":1296,"properties":1302},"8fd65875-79cc-459a-9073-2b76900d0d39",[48],[1297],{"id":9,"sortIndex":15,"affiliation":1298,"properties":9},{"id":1236,"createTime":1237,"updateTime":1237,"relativeEntities":1299,"slug":9,"properties":1300,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},[],{"title":1301},{"VI":1241},{"title":1303},{"VI":1304},"P. Santra",{"url":1227,"publisher":1306,"properties":1313},{"id":6,"createTime":7,"updateTime":7,"relativeEntities":1307,"slug":9,"properties":1308,"entityType":13,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15,"subjectFields":1310,"manageAffiliations":1311,"indexDatabases":1312,"url":9,"thumbnailPath":9,"statistic":9,"gsStatistic":9,"type":9,"analyzePriority":9},[],{"title":1309},{"EN":12},[],[],[],{"pages":1314},{"VOID":1315},"469-472",{"id":1317,"createTime":1318,"updateTime":1319,"relativeEntities":1320,"slug":1321,"properties":1322,"entityType":38,"verifyStatus":39,"verifyTime":1336,"verifyNote":40,"syncStatus":14,"languages":9,"translateLanguages":1337,"viewCount":15,"primaryUrl":1339,"fullTextUrl":1340,"authors":1341,"publicationType":98,"publisherRelationship":1357,"citationCount":9,"citationInfo":9,"publishDate":9,"publishYear":9,"citationAnalyzeStatus":14,"lastCitationAnalyze":9,"indexDatabases":9,"openAccess":9,"references":9,"isForceReanalyzing":110},"9501402a-b636-4837-9b4e-3aa13a3e5bf8","2023-12-22T12:25:51.629+00:00","2025-01-20T20:56:34.065+00:00",[],"Recent-progress-from-the-DIII-D-program",{"references":1323,"keywords":1325,"abstract":1328,"title":1331,"doi":1334},{"VOID":1324},"ferron, 1992, Rev Sci Instr, 63\npenaflor, 2000, Proc 21st Symp Fusion Technology Conf\nferron, 1998, Nucl fusion 38, 1055\nferron, 1996, Proc 16th IEEE\u002FNPSS Symp on Fusion Engineering September 30-October 5 1995 Champaign Illinois, 2, 870\njohnson, 2001, Structure and Feedback Stabilization of the Resistive Wall Mode in DIII-D, Proc 28th EPS Conf on Controlled Fusion and Plasma Physics\nla haye, 2001, Suppression of Neoclassical Tearing Modes int9he Presence of Sawteeth Instabi1ities by Radially Localized Off- axis Electron Cyclotron Current Drive in the DIII-D Tokamak, Proc 28th EPS Conf on Controlled Fusion and Plasma Physics\nlahaye, 0, Control of Neoclassical Tearing Modes in DIII-D, Physics of Plasmas\nhumphreys, 2001, Design Simulation and Operational Use of Control Algorithms for ECCD Suppression of the m\u002Fn =3\u002F2 Neoclassical Tearing Mode ’ Bull Am Phys Soc 46, 299\n10.1109\u002FFUSION.2002.1027659\n10.1063\u002F1.1424233\ndoane, 1993, Int Jour of Infrared and Millimeter Waves, 14\n10.1109\u002FFUSION.2002.1027661\nluce, 1999, Phys Rev Letters, 83, 10.1103\u002FPhysRevLett.83.4550\n10.1063\u002F1.1424196\ncampbell, 1993, Proc 17th Symp Fusion Technology\nburrell, 2001, Physics of Plasmas, 8, 10.1063\u002F1.1355981\n10.1103\u002FPhysRevLett.89.055001\nburrell, 1999, Physics of Plasmas, 6, 10.1063\u002F1.873728\ndoyle, 2000, Progress Towards Increased Understanding and Control of Internal Transport Barriers on DIII-D, 18th IAEA Fusion Energy Conference\n10.1109\u002FFUSION.1995.534365\ngreenfield, 0, Phys Rev Letters, 86\n10.1063\u002F1.1446036\n10.1103\u002FPhysRevLett.89.235001\ngreenfield, 2000, Physics of Plasmas 7 1959\nbialek, 2001, Physics of Plasmas 8 2], 70\nwade, 2001, Physics of High Bootstrap Fraction, High Performance Plasmas on DIII-D Tokamak, Proc 28th EPS Conf on Controlled Fusion and Plasma Physics\n10.1063\u002F1.1424191\n10.1088\u002F0741-3335\u002F44\u002F5A\u002F308\nmurakami, 2001, Advanced Tokamak Scenario Modeling Using Electron Cyc1otron Current Drive in DIII-D, Bull Am Phys Soc, 46\n10.1063\u002F1.1456064\nhoulberg, 1997, Physics of Plasmas, 3230\ntaylor, 1999, Physics of Plasmas, 6\ndoyle, 2001, Recent Results from Quiescent Double Barrier Regime on DIII-D, Bull Am Phys Soc, 46",{"EN":1326,"VI":1327},"Plasma measurements,Tokamaks,Feedback,Coils,Electrons,Control systems,Error correction,Magnetic sensors,Cyclotrons,Predictive models","Đo plasma, Tokamak, Phản hồi, Cuộn dây, Electron, Hệ thống điều khiển, Sửa lỗi, Cảm biến từ tính, Cyclotron, Mô hình dự đoán",{"EN":1329,"VI":1330},"Significant progress has been made in a number of key scientific and engineering areas that are critical to advanced tokamak operation on the DIII-D tokamak. Improved error field correction coupled with plasma rotation has resulted in a passive wall stabilized discharge at twice the no-wall beta limit. Active feedback stabilization of the resistive wall mode (RWM) has been improved using newly installed internal magnetic sensors and external control coils. A set of internal control coils for RWM feedback has been designed that should permit operation at close to the ideal limit. Real-time stabilization of the neoclassical tearing mode has been achieved using a new \"search and suppress\" control algorithm coupled with electron cyclotron current drive (ECCD). The ECCD system is routinely providing in excess of 2 MW of power for 2 s pulses. Modeling predicts that measured efficiencies of ECCD are consistent with future, fully non-inductive AT target discharges. Massive injection of Ar gas has resulted in successful mitigation of disruptions in high performance discharges without producing high energy runaway electrons. Finally, an upgraded digital plasma control system will provide significantly more capability to provide real time measurement and control of plasma profiles and instabilities.","Tiến bộ đáng kể đã được thực hiện trong một số lĩnh vực khoa học và kỹ thuật chính, rất quan trọng cho hoạt động tokamak tiên tiến trên tokamak DIII-D. Việc cải thiện sửa lỗi trường động liên kết với sự quay plasma đã dẫn đến một quá trình phóng điện ổn định thụ động với bức tường ở mức gấp đôi giới hạn beta không có bức tường. Ổn định phản hồi chủ động của chế độ tường điện trở (RWM) đã được cải thiện bằng cách sử dụng các cảm biến từ trường nội bộ mới được lắp đặt và các cuộn điện điều khiển bên ngoài. Một bộ các cuộn điều khiển nội bộ cho phản hồi RWM đã được thiết kế cho phép hoạt động gần với giới hạn lý tưởng. Ổn định thời gian thực của chế độ xé tân cổ điển đã được thực hiện bằng cách sử dụng một thuật toán điều khiển \"tìm kiếm và ngăn chặn\" mới kết hợp với động lực điện tử cyclotron (ECCD). Hệ thống ECCD thường xuyên cung cấp hơn 2 MW công suất cho các xung 2 giây. Mô hình hóa dự đoán rằng hiệu suất đo được của ECCD nhất quán với các phát điện AT mục tiêu hoàn toàn không cảm ứng trong tương lai. Việc bơm khí Ar hàng loạt đã dẫn đến việc giảm thiểu thành công các sự cố trong các quá trình phóng điện hiệu suất cao mà không sinh ra các electron chạy trốn năng lượng cao. Cuối cùng, một hệ thống điều khiển plasma kỹ thuật số được nâng cấp sẽ cung cấp khả năng đáng kể hơn để đo lường và điều khiển thời gian thực các hồ sơ plasma và sự bất ổn định.",{"EN":1332,"VI":1333},"Recent progress from the DIII-D program","Những tiến bộ gần đây từ chương trình DIII-D",{"VOID":1335},"10.1109\u002FFUSION.2002.1027732","2025-01-14T12:46:56.231+00:00",[1338],"VI","https:\u002F\u002Fieeexplore.ieee.org\u002Fabstract\u002Fdocument\u002F1027732\u002F","https:\u002F\u002Fieeexplore.ieee.org\u002Fstamp\u002Fstamp.jsp?tp=&arnumber=1027732",[1342],{"id":1343,"sortIndex":15,"researcher":9,"roles":1344,"affiliations":1345,"properties":1354},"88d8d4d3-9124-4a80-a47f-4d2dd80ce278",[48],[1346],{"id":9,"sortIndex":15,"affiliation":1347,"properties":9},{"id":1348,"createTime":1349,"updateTime":1349,"relativeEntities":1350,"slug":9,"properties":1351,"entityType":60,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15},"8f5eb457-2583-4a31-806f-da021f9f39c8","2023-12-22T12:25:51.645+00:00",[],{"title":1352},{"VI":1353},"The DIII-D Team, General Atomics, San Diego, CA, USA",{"title":1355},{"VI":1356},"A.G. Kellman",{"url":1339,"publisher":1358,"properties":1365},{"id":6,"createTime":7,"updateTime":7,"relativeEntities":1359,"slug":9,"properties":1360,"entityType":13,"verifyStatus":14,"verifyTime":9,"verifyNote":9,"syncStatus":14,"languages":9,"translateLanguages":9,"viewCount":15,"subjectFields":1362,"manageAffiliations":1363,"indexDatabases":1364,"url":9,"thumbnailPath":9,"statistic":9,"gsStatistic":9,"type":9,"analyzePriority":9},[],{"title":1361},{"EN":12},[],[],[],{"pages":1366},{"VOID":1367},"442-447"]