中国核聚变装置首次实现100秒长脉冲氢中性束引出

福多多

坐落于合肥的EAST装置（资料图）

新华社合肥1月5日电(记者蔡敏)记者5日从中科院合肥物质研究院获悉，该院等离子体所承担的大科学工程“人造太阳”实验装置(EAST)又获重大实验成果，其辅助加热工程的中性束注入系统(NBI)在综合测试平台上成功实现100秒长脉冲氢中性束引出，初步验证了系统的长脉冲运行能力。

科学家们介绍说，本轮实验获得的长脉冲中性束引出，在国内尚属首次，标志着中国在中性束注入加热研究领域又迈出了坚实的一步。

EAST装置辅助加热系统2010年7月正式立项，它是使EAST具有运行高参数等离子体的能力，从而可以开展与国际热核聚变反应堆密切相关的最前沿性研究的重要系统。其主要包括低杂波电流驱动系统、中性束注入系统这两大系统。

EAST中性束注入系统完全由中国自行研制，涵盖了精密的强流离子源、高真空、低温制冷、高电压及隔离技术、远程测控及等离子体和束诊断等多个科学技术领域。

本轮实验中，中性束注入系统团队按实验计划仅利用10天的调试，即获得束能量30千电子伏、束流9安培、束功率约0.3兆瓦、脉冲宽度100秒的长脉冲中性束引出。实验在成功测试兆瓦级强流离子源性能的同时，也验证了NBI各子系统具备100秒的长脉冲运行能力。

目前获得的实验结果具里程碑性质，标志着中国自行研制的具国际先进水平的中性束注入加热系统已基本克服重大技术难关，为中性束注入系统在2013年投入EAST物理实验奠定了坚实基础。

中国是国际热核聚变实验堆(ITER计划)的参与国之一。EAST是由中国独立设计制造的世界首个全超导核聚变实验装置，2007年3月通过国家验收，并在近年来取得了一系列实验成果。其科学目标是为ITER计划和中国未来独立设计建设运行核聚变堆奠定坚实的科学和技术基础。


2010年12月24日，一位工作人员从全超导托卡马克（EAST）实验装置前走过。当日，我国新一代“人造太阳”实验装置、世界首个全超导托卡马克（EAST）2010年度实验圆满结束，目前已获得1兆安等离子体电流、100秒1500万度偏滤器长脉冲等离子体、大于30倍能量约束时间高约束模式等离子体、3兆瓦离子回旋加热等多项重要实验成果。新华社记者 郭晨 摄


EAST辅助加热系统NBI主真空室的外形结构（等离子体所尹红星提供）




继2006年9月首次成功放电后，位于合肥的全超导非圆截面核聚变实验装置（EAST）2007年1月14日23时01分至15日1时连续放电四次，单次时间长约50毫秒，从而标志着第二轮物理实验的开始。 新华社 杨文婷 摄




2006年5月26日，各国专家在参观我国自主研制的“人造太阳”。当日，参加第十七届受控聚变装置中等离子体与壁相互作用国际会议的近400名专家，在合肥科学岛参观了我国自主研制的“人造太阳”--全超导托卡马克EAST（原名HT－7U）核聚变实验装置。

Kami

傻蛋吞椰酥

阿三也有：
http://en.wikipedia.org/wiki/SST-1_(tokamak)

傻蛋吞椰酥

看下面的表：

http://en.wikipedia.org/wiki/ADITYA_(tokamak)

傻蛋吞椰酥

在国内尚属首次
=================

只要不是国际上首次，就不算什么。

sbhab

傻蛋吞椰酥 发表于 2013-1-7 05:28 AM
在国内尚属首次
=================

Experimental tokamaks (Quoted from WIKI)

Currently in operation(in chronological order of start of operations)


Alcator C-ModTM1-MH (since 1977 Castor, since 2007 Golem[9]) in Prague, Czech Republic; in operation in Kurchatov Institute since early 1960s; 1977 renamed to Castor and moved to IPP CAS,[10] Prague; 2007 moved to FNSPE, Czech Technical University in Prague, and renamed to Golem.

H-1NF H-1 National Plasma Fusion Research Facility, h1nf[11] based on the H-1 Heliac device built by Australia National University's plasma physics group and in operation since 1992.

T-10, in Kurchatov Institute, Moscow, Russia (formerly Soviet Union); 2 MW; in operation since 1975.

TEXTOR, in Jülich, Germany; in operation since 1978.

Joint European Torus (JET), in Culham, United Kingdom; 16 MW; in operation since 1983.

Novillo Tokamak,[12] at the Instituto Nacional de Investigaciones Nucleares,in Mexico City, Mexico; in operation since 1983.

JT-60, in Naka, Ibaraki Prefecture, Japan; in operation since 1985 (Currently undergoing upgrade to Super, Advanced model).

STOR-M, University of Saskatchewan; Canada in operation since 1987; first demonstration of alternating current in a tokamak.

Tore Supra,[13] at the CEA, Cadarache, France; in operation since 1988.

Aditya, at Institute for Plasma Research (IPR) in Gujarat, India; in operation since 1989.

DIII-D,[14] in San Diego, USA; operated by General Atomics since the late 1980s.

COMPASS,[10] in Prague, Czech Republic; in operation since 2008, previously operated from 1989 to 1999 in Culham, United Kingdom.

FTU, in Frascati, Italy; in operation since 1990.

Tokamak ISTTOK,[15] at the Instituto de Plasmas e Fusão Nuclear, Lisbon, Portugal; in operation since 1991.

Outside view of the NSTX reactor

ASDEX Upgrade, in Garching, Germany; in operation since 1991.

Alcator C-Mod,[16] MIT, Cambridge, USA; in operation since 1992.

Tokamak à configuration variable (TCV), at the EPFL, Switzerland; in operation since 1992.

TCABR, at the University of São Paulo, São Paulo, Brazil; this tokamak was transferred from Centre des Recherches en Physique des Plasmas in Switzerland; in operation since 1994.

HT-7, in Hefei, China; in operation since 1995.

HL-2A, in Chengdu, China; in operation since 2002.

MAST, in Culham, United Kingdom; in operation since 1999.

NSTX in Princeton, New Jersey; in operation since 1999.

Pegasus Toroidal Experiment[17] at the University of Wisconsin-Madison; in operation since the late 1990s.

EAST (HT-7U), in Hefei, China; in operation since 2006.

KSTAR, in Daejon, South Korea; in operation since 2008.

SST-1, in Institute for Plasma Research Gandhinagar, India; 1000 seconds operation.[18]

IR-T1, Islamic Azad University, Science and Research Branch, Tehran, Iran [19]

Previously operated

The control room of the Alcator C tokamak at the MIT Plasma Science and Fusion Center, in about 1982–1983.LT-1, Australia National University's plasma physics group built the first tokamak outside of Soviet Union c. 1963.

T-3, in Kurchatov Institute, Moscow, Russia (formerly Soviet Union);
T-4, in Kurchatov Institute, Moscow, Russia (formerly Soviet Union); in operation in 1968
Texas Turbulent Tokamak, University of Texas, USA; in operation from 1971 to 1980.
Tokamak de Fontenay aux Roses (TFR), near Paris, France
Alcator A and Alcator C, MIT, USA; in operation from 1973 until 1979 and from 1978 until 1987, respectively.
TFTR, Princeton University, USA; in operation from 1982 until 1997
T-15, in Kurchatov Institute, Moscow, Russia (formerly Soviet Union); 10 MW; in operation from 1988 until 2005
UCLA Electric Tokamak, in Los Angeles, United States; in operation from 1999 to 2005
Tokamak de Varennes; Varennes, Canada; in operation from 1987 until 1999; operated by Hydro-Québec and used by researchers from Institut de recherche en électricité du Québec (IREQ) and the Institut national de la recherche scientifique (INRS)
START in Culham, United Kingdom; in operation from 1991 until 1998
COMPASS in Culham; in operation until 2001
HL-1M Tokamak,Chengdu,China; in operation from 1994 to 2001
MT-1 Tokamak, Budapest, Hungary 1979-1998 (Built at the Kurchatov Institute, Russia, transported to Hungary in 1979, rebuilt in 1991 to MT-1M)

Planned

ITER, international project in Cadarache, France; 500 MW, construction began in 2010, first plasma expected in 2020.[20]

DEMO; 2000 MW, continuous operation, connected to power grid. Planned successor to ITER; construction to begin in 2024 according to preliminary timetable.