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The basic regime characteristics of the l = 2 torsatron with additional longitudinal magnetic field coils 附加纵向磁场线圈的l = 2扭转子的基本态特性
Plasma Devices and Operations Pub Date : 2007-10-24 DOI: 10.1080/10519990701562360
V. Kotenko, D. V. Kurilo, Yu. F. Sergeyev, Ye. D. Volkov
{"title":"The basic regime characteristics of the l = 2 torsatron with additional longitudinal magnetic field coils","authors":"V. Kotenko, D. V. Kurilo, Yu. F. Sergeyev, Ye. D. Volkov","doi":"10.1080/10519990701562360","DOIUrl":"https://doi.org/10.1080/10519990701562360","url":null,"abstract":"Numerical studies were carried out to show that a regime implied as the standard or basic regime in the l = 2 torsatrons and heliotrons with no additional longitudinal magnetic field coils can be realized in the l = 2 torsatron with the aforementioned coils. The regime is characterized by a shift in the closed magnetic surface configuration inwards in the torus, by the transformation of the spatial magnetic axis into the planar axis and by close to minimum values of the field ripple at the magnetic surfaces. For the simulation model used, the main parameters of the magnetic surface are given at several values of the additional longitudinal magnetic field.","PeriodicalId":54600,"journal":{"name":"Plasma Devices and Operations","volume":"36 1","pages":"253 - 262"},"PeriodicalIF":0.0,"publicationDate":"2007-10-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81086673","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 4
Study of gas heating in a xenon glow discharge 氙气辉光放电中气体加热的研究
Plasma Devices and Operations Pub Date : 2007-10-24 DOI: 10.1080/10519990701669512
A. Benmoussa, H. Sisabeur, Z. Harrache, A. Belasri
{"title":"Study of gas heating in a xenon glow discharge","authors":"A. Benmoussa, H. Sisabeur, Z. Harrache, A. Belasri","doi":"10.1080/10519990701669512","DOIUrl":"https://doi.org/10.1080/10519990701669512","url":null,"abstract":"In this work, we investigated the effect of gas heating near the electrode of an excimer lamp. Gas heating occurs in the cathode region as ions are accelerated by the high electric field near the cathode. The gas temperature profile was calculated by solving the one-dimensional heat transport equation in the Joule heating approximation without including the effect of reflected particles. The inter-electrode gap was filled with xenon gas and measured 0.5 cm. The model predicts correctly the waveform of the temperature and illustrates the important role of the boundary conditions. The results obtained show clearly that the increase in the temperature in the sheath is limited by the increase in the ion current density in the cathode region due to the electron multiplication.","PeriodicalId":54600,"journal":{"name":"Plasma Devices and Operations","volume":"194 1","pages":"299 - 304"},"PeriodicalIF":0.0,"publicationDate":"2007-10-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83495973","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 2
Test strategy of a Russian ceramic helium-cooled test blanket module in the International Thermonuclear Experimental Reactor 俄罗斯陶瓷氦冷试验包层模块在国际热核实验反应堆中的试验策略
Plasma Devices and Operations Pub Date : 2007-10-24 DOI: 10.1080/10519990701674074
V. Kovalenko, Yu. G. Strebkov
{"title":"Test strategy of a Russian ceramic helium-cooled test blanket module in the International Thermonuclear Experimental Reactor","authors":"V. Kovalenko, Yu. G. Strebkov","doi":"10.1080/10519990701674074","DOIUrl":"https://doi.org/10.1080/10519990701674074","url":null,"abstract":"One of the basic purposes of the International Thermonuclear Experimental Reactor (ITER) programme is to test the elements of test blanket modules (TBMs) of the demonstration fusion reactor DEMO. In the present paper the opportunities for extrapolation of the test results of a Russian demonstration fusion reactor DEMO ceramic helium-cooled blanket TBM in the ITER to the DEMO blanket parameters are considered. A possible research and development plan for the Russian ceramic helium-cooled TBM, the types of TBM for testing in the ITER, and the TBM test plan are presented.","PeriodicalId":54600,"journal":{"name":"Plasma Devices and Operations","volume":"13 1","pages":"305 - 315"},"PeriodicalIF":0.0,"publicationDate":"2007-10-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87146443","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
On heat removal from the first-wall elements and warm toroidal field coils in the JUST-T tokamak JUST-T托卡马克第一壁元件和暖环形场线圈的散热研究
Plasma Devices and Operations Pub Date : 2007-07-19 DOI: 10.1080/10519990701451002
E. Azizov, G. G. Gladush, N. Rodionov, V. Rodionova
{"title":"On heat removal from the first-wall elements and warm toroidal field coils in the JUST-T tokamak","authors":"E. Azizov, G. G. Gladush, N. Rodionov, V. Rodionova","doi":"10.1080/10519990701451002","DOIUrl":"https://doi.org/10.1080/10519990701451002","url":null,"abstract":"Heat removal from the structural elements of a compact tokamak with warm coils intended for the transmutation of minor actinides is an especially critical problem. This paper is concerned with the thermal processes on the first-wall elements and the toroidal field windings, ignoring the most stressed component of JUST-T, i.e. the blanket. The analysis has shown that the peak load on the first-wall elements in JUST-T does not exceed a similar load in the International Thermonuclear Experimental Reactor tokamak. The two-dimensional numerical code for calculation of the current distribution density, Ohmic heating and heat transfer due to heat conductivity and extraction of heat by the water flux has been developed.","PeriodicalId":54600,"journal":{"name":"Plasma Devices and Operations","volume":"48 48 1","pages":"241 - 252"},"PeriodicalIF":0.0,"publicationDate":"2007-07-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79318782","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Application of RGT graphite in fusion devices RGT石墨在聚变装置中的应用
Plasma Devices and Operations Pub Date : 2007-07-19 DOI: 10.1080/10519990701450632
O. Buzhinskij, V. Otroshchenko, W. West
{"title":"Application of RGT graphite in fusion devices","authors":"O. Buzhinskij, V. Otroshchenko, W. West","doi":"10.1080/10519990701450632","DOIUrl":"https://doi.org/10.1080/10519990701450632","url":null,"abstract":"The application of fine-grained recrystallized RGT graphite modified by titanium is considered. Thermally stabilized fine-grained RGT graphite modified by 10 at.% Ti has a density of 2.1 g cm−3, a heat conductivity of up to 800 W m−1 K−1, a low porosity and a small retention of hydrogen isotopes. The paper presents the results of full-scale tests on RGT graphite samples carried out in the T-10 and T-11M tokamaks in Russia, in the DIII-D tokamak in the USA, and in the MK-200 and PLADIS plasma facilities. The tested samples made from RGT graphite were found to be sufficiently stable, in particular, under irradiation for 600 ms by plasma with an electron temperature of 60 eV, an electron density of 2.5×1014 cm−3 and a power of the parallel heat flux of 5 kW cm−2, which are typical for the working modes and disruptions of plasma discharges in tokamaks.","PeriodicalId":54600,"journal":{"name":"Plasma Devices and Operations","volume":"37 1","pages":"201 - 208"},"PeriodicalIF":0.0,"publicationDate":"2007-07-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85325478","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Calculations of current ramp-up scenarios for the Component Test Facility tokamak using the DINA code 使用DINA代码计算组件测试设施托卡马克的当前爬坡方案
Plasma Devices and Operations Pub Date : 2007-07-19 DOI: 10.1080/10519990701451085
A. Dnestrovskij, V. Lukash, R. Khayrutdinov
{"title":"Calculations of current ramp-up scenarios for the Component Test Facility tokamak using the DINA code","authors":"A. Dnestrovskij, V. Lukash, R. Khayrutdinov","doi":"10.1080/10519990701451085","DOIUrl":"https://doi.org/10.1080/10519990701451085","url":null,"abstract":"The free-boundary equilibrium time evolution code DINA is used for calculations of the current ramp-up scenarios in the Component Test Facility (CTF) machine based on the concept of low-aspect-ratio tokamaks. The current ramp-up and subsequent support of the steady phase operation in the CTF is realized by the current driven by the neutral beam (NB), the bootstrap current and the current produced owing to the variation in the poloidal field from the control coils. The problems of seeded current formation are discussed. The self-consistent scenario for current ramp-up for the CTF project is worked out. The steady-state regime parameters are analysed. NB power absorption and current drive calculations are carried out by the DINA code tested on different devices.","PeriodicalId":54600,"journal":{"name":"Plasma Devices and Operations","volume":"10 5 1","pages":"209 - 218"},"PeriodicalIF":0.0,"publicationDate":"2007-07-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82877244","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 3
Numerical simulation of the initial stage of the plasma column formation in JUST-T tokamak JUST-T托卡马克等离子体柱形成初期的数值模拟
Plasma Devices and Operations Pub Date : 2007-07-19 DOI: 10.1080/10519990701450616
A. Barkalov, G. G. Gladush
{"title":"Numerical simulation of the initial stage of the plasma column formation in JUST-T tokamak","authors":"A. Barkalov, G. G. Gladush","doi":"10.1080/10519990701450616","DOIUrl":"https://doi.org/10.1080/10519990701450616","url":null,"abstract":"In this paper, the stage of plasma column formation in the JUST-T tokamak is considered on the basis of a homogeneous model. The ionization, charge exchange, equilibration of temperatures between electrons and ions, radiation losses, Ohmic heating and additional heating are taken into account. With the use of electron cyclotron resonance heating, the breakdown voltage U br decreases from 30 to 16 V for P ECRH=300 kW and p=2 mPa. The additional ion cyclotron resonance heating is less effective; U br=20 V. The optimal conditions for overcoming the ionization radiation barrier were obtained for the JUST-T tokamak.","PeriodicalId":54600,"journal":{"name":"Plasma Devices and Operations","volume":"1 1","pages":"185 - 192"},"PeriodicalIF":0.0,"publicationDate":"2007-07-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73292515","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 2
Features and advantages of boron carbide as a protective coating of the tokamak first wall 碳化硼作为托卡马克第一壁保护涂层的特点和优点
Plasma Devices and Operations Pub Date : 2007-07-19 DOI: 10.1080/10519990701450657
L. Begrambekov, O. Buzhinskij
{"title":"Features and advantages of boron carbide as a protective coating of the tokamak first wall","authors":"L. Begrambekov, O. Buzhinskij","doi":"10.1080/10519990701450657","DOIUrl":"https://doi.org/10.1080/10519990701450657","url":null,"abstract":"The physical aspects of graphites, carbon-fibre composites (CFC) and boron–carbon coatings as plasma-facing materials are considered. The advantages and disadvantages of their applications in tokamaks are analysed. A crystalline boron carbide coating is shown to have excellent erosion characteristics, low hydrogen retention capacity and high resistance under high-energy loads; these properties of boron carbide differ significantly from those of graphite. In modern fusion devices, crystalline boron carbide deposited on graphites with a high thermal conductivity can be used successfully as a plasma-facing material. A new technique suitable for deposition of boron carbide coating in the plasmas of modern tokamaks is described. It is concluded that a thick renewable boron carbide coating can be used successfully under the conditions of the first wall of the International Thermonuclear Experimental Reactor.","PeriodicalId":54600,"journal":{"name":"Plasma Devices and Operations","volume":"21 1","pages":"193 - 199"},"PeriodicalIF":0.0,"publicationDate":"2007-07-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"72950861","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 10
Application of a volumetric neutron source to enhance the use of raw materials in nuclear power from thermal reactors 体积中子源在提高热堆核电原料利用率方面的应用
Plasma Devices and Operations Pub Date : 2007-07-19 DOI: 10.1080/10519990701451119
V. Kotov
{"title":"Application of a volumetric neutron source to enhance the use of raw materials in nuclear power from thermal reactors","authors":"V. Kotov","doi":"10.1080/10519990701451119","DOIUrl":"https://doi.org/10.1080/10519990701451119","url":null,"abstract":"The determinant role of raw uranium usage for atomic power production in the twenty-first century is shown. The limitations of modern reactors are the low fission materials breeding in thermal reactors and the large amount of uranium needed for start-up of fast reactors. Thermal reactor breeding can be increased under the following conditions: a decrease in the neutron losses in structural materials, leakage and operative control, and the use of a closed balanced fuel cycle. In this case, some of the raw 235U in the fuel at the start of the campaign decreases. Replacement of the raw 235U by 233U produced from thorium increases the raw usage up to 100%. The yield of 233U in a fission reactor decreases the burning-out. Production of 233U by a tokamak-based volumetric neutron source (VNS) removes the burning-out limitation. In this case, the energy consumed by the VNS is much less than the gain in the fission reactor energy production.","PeriodicalId":54600,"journal":{"name":"Plasma Devices and Operations","volume":"18 1","pages":"219 - 224"},"PeriodicalIF":0.0,"publicationDate":"2007-07-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74709121","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 3
Non-inductive plasma operation scenario in tokamaks—possibilities for realization 托卡马克中无感等离子体操作场景-实现的可能性
Plasma Devices and Operations Pub Date : 2007-07-19 DOI: 10.1080/10519990701467024
A. Mineev
{"title":"Non-inductive plasma operation scenario in tokamaks—possibilities for realization","authors":"A. Mineev","doi":"10.1080/10519990701467024","DOIUrl":"https://doi.org/10.1080/10519990701467024","url":null,"abstract":"Problems of the plasma scenario realization in a volumetric neutron source of the tokamak type are discussed in the paper, namely the generation of the fore-current followed by the non-inductive plasma current ramp-up up to its basic value.","PeriodicalId":54600,"journal":{"name":"Plasma Devices and Operations","volume":"183 1","pages":"225 - 240"},"PeriodicalIF":0.0,"publicationDate":"2007-07-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85077044","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 1
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