可控核聚变科学技术前沿问题和进展

可控核聚变能源是未来理想的清洁能源。国际磁约束聚变界近期研究的焦点是国际热核聚变实验堆(ITER)项目。本文介绍了ITER计划的科学目标和工程技术目标中的前沿问题,提出了我国磁约束聚变近期、中期和远期技术目标,制定了中国磁约束聚变发展路线图。在惯性约束聚变(ICF)领域,Z箍缩作为能源更具潜力。美国Sandia国家实验室Z/ZR装置的实验进展显著。我国在Z箍缩辐射源物理和驱动ICF技术路线,尤其是在驱动器与Z箍缩负载能量耦合物理方面开展了大量基础研究。笔者建议我国继续执行ITER国际合作计划,全面掌握聚变实验堆技术;积极推进中国聚变工程试验堆(CFETR)主机关键部件研发、适时启动CFETR项目的全面建设;支持新一代大电流脉冲功率实验平台建设,尽快实现Z箍缩聚变点火,探索Z箍缩驱动惯性约束聚变裂变混合堆。     

ITER计划采购包及标准化研究——以核工业西南物理研究院实践为例

参与国际热核聚变实验堆(下称ITER)计划对我国核聚变研究和工程水平发展具有重要的推动意义。本文分析了核工业西南物理研究院执行ITER计划采购包任务以及过程中所涉及标准应用,为我国核聚变标准制定提出建议,旨在为我国未来建设核聚变反应堆打下基础。     

ITER计划中国制造任务首件产品启运

2011年12月2日,中科院等离子所为国际热核聚变实验堆(ITER)计划中国制造任务的首件产品"ITER环向场(TF)超导导体"在安徽合肥举办交付启运仪式。科技部副部长曹健林、ITER国际组织总干事本岛修、中国国际核聚变能源计划执行中心副主任罗德隆等出席仪式。即将交付的全长780米ITER-TF导体是中国ITER采购包的首件正式产品,将用于ITER装置的建造,也是中国     

政府及企业应更多关注和支持超导材料研究及产业发展

低温超导应用方面已具有较好的材料基础张平祥研究员指出，超导材料宏观／微观尺度的均匀性、材料性能／制备技术的综合性价比是实用化超导材料能否大规模应用的关键。大科学工程及NMR（核磁共振）等高端仪器装备将是我国实用化超导材料发展驱动力。通过参与国际热核聚变实验堆计划（ITER），提升了我国低温超导的研发及产业化能力。     

中国将在“十二五”加速聚变能研究

<正>"十二五"期间,中国将以参加国际热核聚变实验堆(ITER)装置建设为契机,启动实施核聚变能研究专项,加速开展聚变能发展研究。     

西部超导公司成功承接ITER用超导股线合同

<正>2010年12月20日,由西安经济技术开发区管委会主办的西部超导材料科技有限公司与中国国际核聚变能源计划执行中心"国际热核聚变实验堆(ITER)用超导股线"合同的签约仪式在西安经开区经发会馆隆重举行。这标志着     

“国际热核实验反应堆(ITER)计划背景和情况”报告会在北京科技大学召开

【本刊讯】(记者卢利平)2011年7月21日,国际热核实验(ITER)计划背景和情况报告会在北京科技大学学术报告厅举行。北京科技大学葛昌纯院士、燕青芝教授、周张健教授、沈卫平教授、刘维良教授等出席报告会,中国仪表功能材料学会唐逾副秘书长也出席了报告会。报告人罗德隆是中国国际核聚变能源计划执行中心副主任,国际热核实验聚变堆中国采购包的主要负责人,是我国科技部领导核聚变发展的主要领导人之一。他积极组织领导完成我国ITER承担的采购包任务,他所领导的我国ITER采购包任务是所有项目成员国中完成最好的。     

日本开始批量生产ITER用Nb3Sn超导体

日本原子能研究开发机构和新日铁公司在福冈县北九州市合作建成用于国际核聚变实验堆（ITER）的超导线圈用材料Nb3Sn生产厂，3月份开始正式生产。超导材料NbsSn用于制作环向磁场线圈（TF线圈）。     

液化空气获两项极端低温领域设备合同

<正>2013年年初,法国液化空气集团获得总价超过1亿欧元的两项极端低温系统设备销售合同。其中一项合同涉及位于法国马赛附近的国际热核聚变实验堆(ITER)计划,另一项是位于日本那珂市的JT-60SA项目。     

国际热核实验反应堆（ITER）真空室的设计介绍

国际热核实验反应堆(ITER)是建造中的世界上最大的聚变反应堆,目前选址已确定在法国的卡达拉奇.这是一项国际合作计划,参加合作的六方为:欧盟、俄罗斯、日本、中国、韩国和美国.ITER设计的宗旨是"演示聚变能和平应用的科学和工艺可行性".主要介绍ITER-FEAT真空室的设计.     

聚变-裂变能源混合堆可行性及在我国核能发展中作用的分析

简要论述了核能在我国能源发展战略中的地位及聚变-裂变混合堆在核能持续发展中的重要作用。对以不久将来即可实现的ITER聚变装置作驱动堆芯、天然铀水冷裂变系统作包层的混合堆做了细致的分析。这种混合堆型可以实现GWe级净电功率输出,年造钚1 656 kg,支持2.68个同功率压水堆电站对易裂变燃料的需要。初步的经济评估说明,混合堆电的成本是同功率压水堆电成本的1.67倍;而在不计燃料成本的情况下,混合堆与压水堆组合系统电的成本是同功率压水堆电成本的1.18倍。考虑到一般压水堆需消耗大量的天然铀,加上铀浓缩成本,混合堆与压水堆组合系统电的成本,与压水堆电的成本是可以相比拟的。     

不同辐照粒子下钨及钨合金辐照损伤行为的研究进展

研究核聚变、准稳态等离子体下面向等离子体材料的辐照行为,发展适合于先进实验超导托卡马克(EAST)、国际热核聚变实验堆(ITER)和中国聚变工程实验堆(CFETR)长脉冲高参数运行乃至未来聚变反应堆稳态运行的高性能面向等离子体材料是当前核聚变研究一项艰巨而又紧迫的任务。钨因具有高熔点、高导热率、低溅射腐蚀速率、高自溅射阀值以及低蒸气压和低氚滞留等优异性能,被认为是聚变装置最具有前景的面向等离子体材料。综合评述了钨及钨合金在不同辐照粒子下损伤行为的最新研究进展。粒子辐照造成的微观缺陷在钨及钨合金内部累积,辐照造成缺陷的形成和数量与钨基材料颗粒微观结构、第二相成分等密切相关,辐照缺陷情况各异。同时,辐照粒子种类、能量、剂量和温度等辐照条件都会对钨材料辐照后的形貌特征和缺陷产生重要影响。     

Stand der Kernfusionsforschung

The aim of nuclear fusion research is to reproduce on earth the energy generating process of the sun and derive energy from the fusion of atomic nuclei. This is to be done by confining the fuel, a low-density hydrogen plasma, in magnetic fields and heating it to high temperatures of over 100 million degrees. Research has made major progress on the way to a burning plasma. JET, the joint European experiment, is just a factor of 6 short of achieving plasma ignition. ITER, the test reactor now being planned in international cooperation, is intended to produce the first burning plasma providing energy over a long period.     

Evaluation of a method to reduce the redeposition of hydrogenated coatings containing carbon and tungsten in fusion reactors

The International Thermonuclear Experimental Reactor (ITER) project will be the first experimental fusion reactor with the objective to demonstrate the scientific and technological feasibility of fusion energy for commercial energy production. Erosion of materials by physical sputtering is the most fundamental of plasma-surface interactions in fusion reactor devices. Carbon and tungsten materials planned to be used in ITER divertor will be subjected to erosion, which produces local redeposition of mixed layers. Tritium retention in mixed materials is the major concern due to the limits imposed for safety reasons by nuclear licensing. The scavenging effect to reduce the redeposition phenomenon has been reported in low-pressure technical plasmas. In the present work, the minimization of co-deposits of hydrogenated C/W coatings by the injection of scavenger particles is analyzed.     

聚变堆非电应用的研究进展(英文)

近几十年来,ITER(国际热核实验堆)计划在为将来提供商业用电研究方面取得了较大的进展。ITER首先打算搭建一个实验聚变堆,然后再建设一个商业示范聚变堆为今后的正式商业发电做出一定的铺垫。但根据如今世界范围内的研究进展,实现聚变堆的商业发电至少要在2050年。在此之前有必要扩大聚变堆的研究范围,因此聚变堆的非电应用研究必须受到足够的重视。聚变堆的非电应用研究包括短期应用研究和长期应用研究,短期应用研究主要体现在医学、危险物的检测等领域的研究,长期应用研究主要体现在嬗变、氢的制备、空间助推器等领域的研究。综述了聚变堆在各个方面的非电应用研究,并且讨论和举证了聚变堆非电应用的可行性。     

Design of the DEMO Fusion Reactor Following ITER

Runs of the NSTAB nonlinear stability code show there are many three-dimensional (3D) solutions of the advanced tokamak problem subject to axially symmetric boundary conditions. These numerical simulations based on mathematical equations in conservation form predict that the ITER international tokamak project will encounter persistent disruptions and edge localized mode (ELMS) crashes. Test particle runs of the TRAN transport code suggest that for quasineutrality to prevail in tokamaks a certain minimum level of 3D asymmetry of the magnetic spectrum is required which is comparable to that found in quasiaxially symmetric (QAS) stellarators. The computational theory suggests that a QAS stellarator with two field periods and proportions like those of ITER is a good candidate for a fusion reactor. For a demonstration reactor (DEMO) we seek an experiment that combines the best features of ITER, with a system of QAS coils providing external rotational transform, which is a measure of the poloidal field. We have discovered a configuration with unusually good quasisymmetry that is ideal for this task.     

Shielding design of the ITER NBI duct for nuclear and bremsstrahlung radiation

Three-dimensional Monte Carlo shielding analyses are conducted on the ITER Neutral Beam Injection (NBI) duct for the nuclear and bremsstrahlung radiation. The detailed distribution is evaluated about the nuclear heating rate and surface heat load of the NBI duct wall by the neutron and photon transport calculation. The analytical representations of these nuclear responses are established as a function of the distance from the blanket surface. It is clarified that these representations are different between the duct wall facing the plasma and that hidden from the plasma, and also between the duct wall in the blanket region and that in the vacuum vessel region. These results are very useful for the shielding design of the NBI duct wall in the nuclear fusion reactor.     

磁体用Nb3Sn超导体研究进展

Nb3Sn是典型的低温超导材料,主要应用于高能物理(HEP)和热核聚变(ITER)以及高场核磁共振(NMR)等磁体领域.Nb3Sn材料在2K时的上临界场Hc2达到30T,为其在高场磁体的应用提供了契机.综述了Nb3Sn的发展现状与研究成果,以及近年来其制备工艺的改进和存在的问题.     

Plasma-surface interaction in ITER

The decreasing availability of energy and the concern about climate change necessitate the development of novel sustainable energy sources. Fusion energy is such a source. The ultimate potential of fusion energy is very high and badly needed. A major step forward in the development of fusion energy is the decision to construct the experimental test reactor ITER.ITER will stimulate research in many areas of science. This article discusses research opportunities in the context of plasma-surface interaction. The fusion plasma with a typical temperature of 10 keV has to be brought into contact with a physical wall in order to remove the helium produced and drain the excess energy in the fusion plasma. The fusion plasma is far too hot to be brought into direct contact with a physical wall. It would degrade the wall and the debris from the wall would extinguish the plasma. Therefore, schemes are developed to cool down the plasma. The resulting plasma-surface interaction concerned in ITER is facing several challenges including surface erosion, material redeposition and tritium retention. In this article we introduce how plasma-surface interaction relevant for ITER can be studied in a smaller scale experiment: Magnum-PSI.