国际热核聚变实验堆(ITER)计划

聚变能目前是认识到的可以最终解决人类能源和环境问题的最重要的途径之一，经过许多科学工作者半个多世纪的努力，磁约束聚变研究取得了重大的进展，集成当今国际受控磁约束核聚变研究的主要科学和技术成果，合作建立与未来实用聚变堆规模相比拟的受控热核聚变实验堆ITER(international thermonuclear experimental reactor)，成为国际上大家的共识，文章就ITER及相关的情况进行一些介绍。     

Thermonuclear Power Engineering: 60 Years of Research. What Comes Next?

This paper summarizes results of more than half a century of research of high-temperature plasmas heated to a temperature of more than 100 million degrees (10⁴ eV) and magnetically insulated from the walls. The energy of light-element fusion сan be used for electric power generation or as a source of fissionable fuel production (development of a fusion neutron source—FNS). The main results of studies of tokamak plasmas which were obtained in the Soviet Union with the greatest degree of thermal plasma isolation among all other types of devices are presented. As a result, research programs of other countries were redirected to tokamaks. Later, on the basis of the analysis of numerous experiments, the international fusion community gradually came to an opinion that it is possible to build a tokamak (ITER) with Q > 1 (where Q is the ratio of the fusion power to the external power injected into the plasma). The ITER program objective is to achieve Q = 1–10 for a discharge time of up to 1000 s. The implementation of this goal does not solve the problem of a steadystate operation. The solution to this problem is a reliable first wall and current generation. This is a task of the next fusion power plant construction stage, called DEMO. Comparison of DEMO and FNS parameters shows that, at this development stage, the operating parameters and conditions of these devices are identical.     

Review of LIBS application in nuclear fusion technology

Nuclear fusion has enormous potential to greatly affect global energy production. The next-generation tokamak ITER, which is aimed at demonstrating the feasibility of energy production from fusion on a commercial scale, is under construction. Wall erosion, material transport, and fuel retention are known factors that shorten the lifetime of ITER during tokamak operation and give rise to safety issues. These factors, which must be understood and solved early in the process of fusion reactor design and development, are among the most important concerns for the community of plasma–wall interaction researchers. To date, laser techniques are among the most promising methods that can solve these open ITER issues, and laser-induced breakdown spectroscopy (LIBS) is an ideal candidate for online monitoring of the walls of current and next-generation (such as ITER) fusion devices. LIBS is a widely used technique for various applications. It has been considered recently as a promising tool for analyzing plasma-facing components in fusion devices in situ. This article reviews the experiments that have been performed by many research groups to assess the feasibility of LIBS for this purpose.     

Concept of Plasma Heating and Current Drive Neutral Beam System for Fusion Neutron Source DEMO-FNS

Steady-state operation of a fusion neutron source (FNS) requires plasma heating and current drive by means of additional power delivered by neutral beams. Six neutral beam injectors (NBI) will provide the DEMO-FNS machine with additional heating power up to 30 MW, with neutral particle energy of 500 keV. NBI systems developed for ITER can serve as the prototype for DEMO-FNS, as both systems have similar ion source current, with accelerated beam power in ITER NBI (1MeV) being twice as large as in DEMOFNS. The paper describes the NBI system with account of its integration into DEMO-FNS tokamak complex.     

Fusion at the crossroads towards ITER

The decision to build ITER in Europe, at Cadarache, as a joint enterprise of all major partners in international fusion research opens a new era for fusion and is expected to focus a strong world-wide effort towards ITER and ITER-related R&D in fusion physics and technology.ITER, the unique Next Step device in magnetic fusion, aims at demonstrating the scientific and technological feasibility of fusion. A solid basis exists for constructing ITER and physics scenarios, diagnostics and technologies are being developed for the desired operational features and performance.The ITER project will be the central priority of the European and international fusion programmes. It will be put in the context of a broader approach of supporting R&D and preparations of the following step, DEMO. A vigorous European accompanying programme must comprise support to ITER and DEMO oriented activities, in particular fusion reactor technologies, the investigation of concept improvements and the corroboration of the theoretical foundations of magnetic confinement and of relevant technologies. The domestic programme will have a crucial role for securing the human potential needed for ITER and for ensuring a leading position in the competitive developments for ITER and the further development of commercial fusion energy.     

The path to fusion power

Fusion, which powers the sun and stars, is potentially an environmentally responsible and intrinsically safe source of essentially limitless energy. The Joint European Torus (JET) has produced 16 MW of fusion power, and construction of a power station sized device called ITER (International Tokamak Experimental Reactor), which should produce at least 500 MW, is about to begin. Further work on fusion technologies is also needed, including construction of the proposed International Fusion Materials Irradiation Facility (IFMIF) which will test materials that will have to stand up to years of intense neutron bombardment in a fusion power station. Given i) its potential attractions (which include essentially limitless fuel, and the absence of green-house gas and of long-lived radio-active by-products), and that ii) it looks as if the economics of fusion power will be acceptable, the time has come to develop fusion as rapidly as reasonably possible. The status and potential advantages of fusion are being described, together with the outstanding challenges, the remaining steps and a timetable for developing fusion power.     

ITER数据库和HL-1M装置等离子体约束特性

ITER数据库是全世界聚变专家通过多年的努力,建立起来的一个旨在研究各种等离子体行为的数据库,并由此得到了一系列的定标律。在介绍了ITER约束数据库的构成和相应的能量约柬定标律之后,介绍了HL-1M托卡马克的数据特点,给出了欧姆加热条件下利用回归分析方法得到的能量约束幂指数定标律,最后对结果进行了分析和讨论。     

氘氚聚变中子发生器旋转氚靶传热特性研究

强流氘氚中子发生器可用于模拟聚变堆中子环境, 对于开展聚变堆包层材料相关实验研究具有重要意义. 本文提出了一种用于10¹² n·^-1量级氘氚中子发生器HINEG (high intensity neutron generator)的旋转氚靶系统设计方案, 并对其技术难点和强化传热方法进行了介绍. 为考查该氚靶系统的传热特性, 利用Computational Fluid Dynamics方法对冷却水层厚度、冷却水流速和氚靶系统旋转速度对靶面冷却的影响进行了分析, 并对不同热功率密度下靶面的传热过程进行了研究. 结果显示, 大的水层厚度、大的冷却水流速和高的靶系统旋转速度有利于靶面的冷却, 但水层厚度和水流速的变化对靶面传热影响较小. 一定条件下靶面所承受的热功率密度不能超过某个限值.     

The ITER project

ITER (the International Thermonuclear Experimental Reactor) is an international collaborative project aimed at demonstrating the scientific and technological feasibility of fusion energy for peaceful purposes. It is the next step for the magnetic fusion development programs of the four participants-the European Union, Japan, Russia, and the United States. This paper reports progress of the engineering design activities (EDA) for ITER. ITER's position in the four parties' fusion programs is outlined, the main elements of the design are introduced, and progress is summarized in physics and technology R&D that support the design activities. The outlook for the future is reviewed, particularly the desirability of making timely progress toward construction of ITER     

JET: Preparing the future in fusion

JET (Joint European Torus) is the largest tokamak in the world and the only fusion facility able to operate with Tritium, the fusion fuel, and Beryllium, the ITER first wall material. JET also features the most complete remote handling equipment for invessel maintenance. As a multinational research center, JET provides logistic experience in preparing for operation of the global facility, tokamak ITER.Experiments on JET are focused on ITER-relevant studies, in particular on detailing the operational scenarios (EL My H-modes and advanced regimes), on enhancing the heating systems, on developing diagnostics for burning plasmas etc. Pioneering real-time control techniques have been implemented that maximize performance and minimize internal disturbances of JET plasmas. In helium plasmas, ion cyclotron heating (ICRH) created fast α-particles, mimicking their populations in future burning plasmas. The recent successful Trace Tritium campaign provided important new data on fuel transport. Current enhancements on JET include a new ITER-like ELM-resilient high power ICRH antenna (7 MW) and over twenty new diagnostics that will further extend the JET scientific capabilities and push the facility even closer to the ITER parameters.A special mention is given to the involvement of the fusion experts from Association EURATOM-IPP.CR, who have been actively participating in the collective use of JET facility for more than three years.     

国际热核实验反应堆(ITER)计划与未来核聚变能源

能源短缺和环境恶化是人类社会面临的共同挑战.由于资源丰富、环境友好和零碳排放,核聚变能源是未来的理想能源.上世纪90年代以来,磁约束核聚变研究取得重大进展,以建造国际热核实验反应堆(ITER)为标志,聚变能源开发进入工程实施阶段,如果ITER计划取得预期成果,有望在本世纪中叶实现核聚变能源商用化.     

ITER聚变功率关闭系统的一种阀门箱结构的有限元分析

用ANSYS软件对ITER聚变功率关闭系统(FPSS)的一种阀门箱的结构在ITER各种典型荷载组合下的应力和应变进行了有限元分析,并遵照ASME及ITER标准对分析结果进行了评判。结果表明这种阀门箱结构能够满足ITER的设计要求。     

Review of Muon Catalyzed Fusion Experiments – Activities after EXAT98 and Future Perspectives

Since EXAT98 at Ascona, significant progress has been marked for experimental investigations of the fundamental understanding of muon catalyzed fusion (μCF) phenomena in D–T, D₂ and other hydrogen systems. Future progress in the μCF studies is now guaranteed due to the successful launching of advanced accelerator projects such as JAERI-KEK Joint Proton Accelerator project and RI Beam Factory project at RIKEN. Also, the start of the next-phase thermal nuclear fusion project of ITER becomes promising so that some future contributions from ITER to μCF or vice-versa can be expected for various physical or technological aspects of fusion research. The future progress of μCF studies will also be promoted because of the growth of various other scientific research using muons. The essence of all these subjects is reviewed. This revised version was published online in August 2006 with corrections to the Cover Date.     

ITER纵场的电磁分析与电源系统的概念设计

进行了ITER纵场磁体电源系统的概念设计.首先,对ITER主机基于循环对称算法,借助ANSYS软件进行了电磁的分析,然后根据电磁分析得到的结果,设计了ITER纵场磁体电源的拓扑结构,分析了整流器的输出电压波形;其次,基于电磁分析的结果,设计了ITER纵场磁体失超保护系统,并计算了磁体失超保护电路中的关键部件-电容和电阻...     

Progress in neutron diagnostics at JET

In the ITER tokamak, diagnosing the plasma neutron emission will be essential to characterise fusion burning process and determine the performance of the machine. JET, currently the world largest tokamak, is the most suitable test bed for development of the fusion-relevant neutron diagnostics due to its plasma parameters and unique tritium operation capability. Current works aim at improving the spatial and spectral characteristics of the neutron measurements at JET, as well as on technological tasks. The present enhancements of neutron diagnostics and data analyses at JET make-together with new fast particle measuring techniques and tritium retention studies-part of the “burning plasma” diagnostic developments towards reactor-grade fusion facilities.     

Wendelstein 7‐X: An Alternative Route to a Fusion Reactor

With the ITER tokamak magnetic confinement fusion is making the decisive step to realize a burning fusion plasma and prepare the basis for a demonstration power plant (DEMO). Despite the advantages of an intrinsically steady state magnetic field and better stability properties, the development of stellarators lags behind by about 1 1/2 device generations, because of the difficulties to realize the desired magnetic field configuration. The goal of the optimized stellarator Wendelstein 7‐X is to overcome the principal deficiencies of the stellarator concept and demonstrate its reactor capability, combining sufficiently good thermal and fast ion confinement with reactor relevant ß and collisionality under steady state conditions. (© 2009 WILEY‐VCH Verlag GmbH & Co. KGaA, Weinheim)     

美国激光惯性约束聚变能源研究综述

简要地介绍了美国激光惯性约束聚变能源( LIFE ) 的研究现状与发展前景。基于美国国家点火装置( NIF ) 的近期进展,美国利弗莫尔实验室提出了激光惯性约束聚变能源设想,并开始了分解研究。设想用新型二极管泵浦固体激光器产生1.4~2.0 MJ 的激光能量,靶丸聚变增益25~30,打靶频率10~15Hz,实现350~500 MW聚变功率,相当于聚变中子源强1.3×1020 ~1.8×1020 n/s。以此驱动次临界裂变包层,使能量再倍增4~10 倍,实现1 GW电功率的输出。采用创新设计的燃料元件,包层可达到90%以上的燃耗深度,形成一个安全、无碳、燃料资源丰富、核废料少、可持续发展的新型核能源系统。In this paper the present study situation and prospect of the American laser-based Inertial Confinement Fusion Energy ( LIFE ) are briefly introduced. It is based on recent progress of National Inertial Facility ( NIF ) and related research have begun. On the assumption of using laser energy of 1.4 to 2.0 MJ, the target fusion gain G=25~30, the repetition rate 10 to 15 Hz, the fusion power of 350 to 500 MW or neutron source power of 1.3×1020 to 1.8×1020 n/s could be achieved. For a sub-critical fission blanket driven by this fusion neutrons power, energy multiplication M of 4~10 and several GW of thermal power could be obtained. By novel design on fuel pins, burnup more than 90% would be achieved for heavy metals in the blanket. Inertial Confinement Fusion-fission energy is a promising concept, which characterized by inherent safety, richness in nuclear fuel resources, minimization of nuclear waste, non-CO2 emitting ,and it is a sustainable energy source.     

磁约束聚变的进展与球形环

自１９９１年１１月以来,从ＪＥＴ、ＴＦＴＲ和ＪＴ－６０Ｕ装置的氘－氚聚变系统运行中所获得的有价值的成果表明,现已有能力研究和设计ＩＴＥＲ和先进的托卡马克型聚变堆．ＩＴＥＲ分两个阶段的设计活动（ＣＤＡ、ＥＤＡ）可于１９９８年７月完成,其中包括安全分析及实验评估在内的聚变动力堆的设计全过程．但昂贵的建造费用已成为ＩＴＥＲ进一步开发的主要矛盾,一种改进型托卡马克——球形环有可能会解决这个问题,主要借助于最小尺寸和简化结构来降低费用．文中描述了动力、实验球形环和混合堆的特征与初步参数． Since Nov. 1991 JET, TFTR, JT 60U have contributed to valuable operating experience with D T reaction systems, and have validated abilities to design ITER. Two steps of ITER design (CDA, EDA) will be finished in July 1998. The whole design process of fusion power reactor has been considered in detail, including safety analysis and experimental valuations, but the high cost of construction becomes a main contradiction in futher developent. An advanced type of Tokamak spherical torus might...     

中国氦冷固态TBM对ITER环向场线圈能量沉积的影响

基于国际热核实验堆(ITER)的Alite 模型和中国氦冷固态陶瓷试验包层模块 (CN HCCB TBM),对装载了CN HCCB TBM后ITER装置的环向场线圈(TFC)的能量沉积的分布和CN HCCB TBM对能量沉积的影响进行了计算分析。结果表明,放入CN HCCB TBM 会使TFC能量沉积减小了3%左右,不会使TFC能量沉积情况恶化;TFC能量沉积主要位于内侧的14个扇区,TFC包壳和超导材料的功率密度的最大值低于限值,满足要求。     

ITER中子屏蔽结构的设计与分析

在ITER真空室的双层壳体之间嵌入中子屏蔽结构用来屏蔽聚变反应中产生的中子流和降低环向磁场的波纹度,从而确保聚变反应的安全进行。阐述了中子屏蔽结构的概念设计、设计准则、详细设计、装配方案等整个设计过程。选取组成整个中子屏蔽结构的一个屏蔽块作为研究对象,通过分载荷步对其进行了热-结构耦合分析,获得各部件响应应力均小于许用应力,满足ITER国际组的设计要求,从而验证了中子屏蔽结构设计的合理性。