Experimental Advanced Superconducting Tokamak

{{Short description|Experimental tokamak}}

{{Infobox fusion devices

|name = EAST

|fullname = Experimental Advanced Superconducting Tokamak

|image = EAST Tokamak vacuum vessel 2015.jpg

|imagetitle = EAST vacuum vessel

|type = Tokamak

|city = Hefei

|state =

|country = China

|affiliation = Hefei Institutes of Physical Science, Chinese Academy of Sciences

|major_radius = {{cvt|1.85|m}}

|minor_radius = {{cvt|0.45|m}}

|volume =

|field = {{cvt|3.5|T}}

|heating = {{val|7.5|ul=MW}}

|power =

|time = {{val|102|ul=s}}

|current = {{val|1.0|ul=MA}}

|temperature = {{val|100|e=6|ul=K}}

|construction_date =

|operation_start_year = 2006

|operation_end_year =

|ongoing = yes

|prev = HT-6M

|next =

|related =

|website =

|other_links =

}}

{{Chinese

| c=先进超导托卡马克实验装置

| p=xiānjìn chāodǎo tuōkǎmǎkè shíyàn zhuāngzhì

| l= Advanced Superconducting Tokamak Experimental device

| showflag = p

}}

File:EAST-tokamak sketch.png

File:EAST Tokamak plasma images.jpg in EAST]]

The Experimental Advanced Superconducting Tokamak (EAST), also known as HT-7U (Hefei Tokamak 7 Upgrade), is an experimental superconducting tokamak magnetic fusion energy reactor in Hefei, China. Operated by the Hefei Institutes of Physical Science conducting its experiments for the Chinese Academy of Sciences, EAST began its operations in 2006. EAST is part of the international ITER program after China joined the initiative in 2003{{Cite web |title=China's New Thermonuclear Fusion Reactor Test Successful -- china.org.cn |url=http://www.china.org.cn/english/2006/Sep/182561.htm |access-date=2024-12-03 |website=www.china.org.cn}} and acts as a testbed for ITER technologies. On January 20, 2025, it sustained plasma for 1066 seconds.

It is the first tokamak to utilize superconducting toroidal and poloidal magnets.

History

EAST followed China's first superconducting tokamak device, dubbed HT-7, built by the Institute of Plasma Physics in partnership with Russia in the early 1990s.{{fact|date=September 2021}} It was first proposed in 1996 and approved in 1998. According to a 2003 schedule,[http://202.127.205.62/IAC/disk/Design%20of%20the%20EAST(HT-7U) Project/6.doc] {{dead link|date=February 2016}} buildings and site facilities were to be constructed by 2003. Tokamak assembly was to take place from 2003 through 2005. Construction was completed in March 2006.{{cite web|url=http://www.china.org.cn/english/2006/Sep/182561.htm |title=China's New Thermonuclear Fusion Reactor Test Successful |publisher=China.org.net |date=September 29, 2006}}

According to official reports, the project's budget is CNY ¥300 million (approximately US$37 million), some 1/15 to 1/20 the cost of a comparable reactor built in other countries.{{cite news|url=http://english.people.com.cn/200601/21/eng20060121_237208.html|title=China to build world's first "artificial sun" experimental device

| publisher=People's Daily Online|date=2006-01-21}}

= Phase I =

EAST entered its first commissioning phase around March 2006. Shortly after, in-vessel components and diagnostics were assembled.https://fire.pppl.gov/iaea06_ov1_1_wan.pdf

During initial operation, EAST was able to successfully generate its first plasma on September 28, 2006 in a nearly three second long test, reaching an electric current of 200 kiloamperes. By January 2007, the reactor had progressed to creating a plasma that could last nearly five seconds and generate currents up to 500 kiloamperes.[https://web.archive.org/web/20100121032440/http://news.xinhuanet.com/english/2007-01/15/content_5608276.htm Xinhua article Jan 15, 2007 Chinese scientists conduct more tests on thermonuclear fusion reactor. 2007-Jan-15]

Three years later, EAST was able to achieve a key milestone on November 7, 2010, achieving an H-mode plasma by low hybrid wave (LHW) injection alone.{{Cite web |last=admin |date=2010-12-03 |title=EAST Tokamak achieves stationary H-mode plasmas |url=https://www.iter.org/node/20687/east-tokamak-achieves-stationary-h-mode-plasmas |access-date=2024-12-03 |website=ITER - the way to new energy |language=en}}{{Better source needed|date=December 2024 |reason=Currently, only a low-quality citation that doesn't mention LHW injection was able to be located.}} This was shortly followed by further success, where EAST became the first tokamak to successfully sustain H-Mode plasma for over 30 seconds at ~50 million Kelvin in May of 2011.

= Phase II =

The second phase of EAST was formally entered through a ribbon-cutting ceremony for the EAST auxiliary heating system project, which was held on November 29, 2011.{{Cite web |title=Institute of Plasma Physics Chinese Academy Of Scieneces |url=http://english.ipp.cas.cn/syxw/201112/t20111203_85861.html |access-date=2024-12-03 |website=english.ipp.cas.cn}}

After a nearly 20-month long upgrading break since September 2012, EAST commenced for the first round of experiments in May 2014. A year later, EAST was reporting currents of up to 1 Megaampere, as well as stable H-mode plasma for 6.4 seconds.[http://english.ipp.cas.cn/rh/east/ EAST at IPP-CAS] Then, almost two years later, EAST was able to break records when it managed to maintain a plasma pulse for 102 seconds at ~50 million °C (90 million °F). During this test, EAST was able to generate a Plasma with currents of 400 kiloamperes with a density of about 2.4 x 1019/m3. It was observed that the temperature was slowly increasing during this test.{{cite web |date=February 6, 2016 |title=That's cute, Germany – China shows the world how fusion is done |url=https://www.theregister.co.uk/2016/02/06/china_shows_how_fusion_is_done/ |publisher=The Register}} more data in screen shot

Building on this success, EAST became the first tokamak to successfully sustain H-Mode plasma for more than one minute at ~50 million °C (90 million °F) on November 2, 2016.{{cite web |url=http://english.ipp.cas.cn/syxw/201611/t20161115_170479.html |title=EAST Achieves Longest Steady-state H-mode Operations |publisher=EAST team |date=November 15, 2016}} In July of 2017, it was also the first tokamak to sustain said plasma for more than 100 seconds at the same temperature.{{cite web |url=https://www.eurekalert.org/pub_releases/2017-07/caos-cs070517.php |title=China's 'artificial sun' sets world record with 100s steady-state high performance plasma |publisher=Chinese Academy of Sciences |date=July 5, 2017}} The following year, EAST reached a milestone of ~100 million °C (180 million °F) electron temperature on November 12, 2018.{{cite web|url=https://phys.org/news/2018-11-chinese-fusion-tool-million-degrees.html|title=Chinese fusion tool pushes past 100 million degrees|publisher=Phys.org|date=November 15, 2018|access-date=August 10, 2020}} During May of 2021, it reached an electron temperature of 120 million °C electron temperature for 101 seconds.{{Citation|title=GLOBALink {{!}} "Chinese artificial sun" sets new world record| date=28 May 2021 |url=https://www.youtube.com/watch?v=IylinT7eKE8|language=en|access-date=2021-05-29}} On December 30, 2021, a long-pulse high-parameter plasma operation of 1056 seconds was realized, setting another world record for the operation of the Tokamak experimental device.{{Citation|title=GLOBALink {{!}} 中国"人造太阳"实现千秒级等离子体运行|url=http://www.news.cn/politics/2021-12/31/c_1128221002.htm|language=en|access-date=2021-12-31}}{{cite web|url=http://english.ipp.cas.cn/news/202112/t20211231_295486.html|title=1,056 Seconds, another world record for EAST|date=December 31, 2021}}

EAST achieved the world's first 403-second steady-state H-mode plasma on April 12, 2023.{{cite web|url=https://english.cas.cn/newsroom/news/202304/t20230417_329388.shtml|title=Reliable 403 Seconds Stationary H-mode Plasmas Demonstrated on EAST|date=April 17, 2023}}

EAST then broke its record several years later on January 20, 2025, when it sustained plasma for 1066 seconds.{{Cite web |author1=Patrick Pester |date=2025-01-21 |title=China's 'artificial sun' shatters nuclear fusion record by generating steady loop of plasma for 1,000 seconds |url=https://www.livescience.com/planet-earth/nuclear-energy/chinas-artificial-sun-shatters-nuclear-fusion-record-by-generating-steady-loop-of-plasma-for-1-000-seconds |access-date=2025-01-22 |website=livescience.com |language=en}}

Physics objectives

China is a member of the ITER consortium, and EAST is a testbed for ITER technologies.{{Cite journal|date=2015|title=Study of lower hybrid current drive towards long-pulse operation with high performance in EAST|series=AIP Conference Proceedings |volume=1689 |page=080002 |publisher=EURATOM|doi=10.1063/1.4936525|bibcode=2015AIPC.1689h0002D |doi-access=free |last1=Ding |first1=B. J. |last2=Li |first2=M. H. |last3=Li |first3=Y. C. |last4=Wang |first4=M. |last5=Shan |first5=J. F. |last6=Liu |first6=F. K. |last7=Wang |first7=S. L. |last8=Wei |first8=W. |last9=Xu |first9=H. D. |last10=Zhao |first10=L. M. |last11=Hu |first11=H. C. |last12=Jia |first12=H. |last13=Cheng |first13=M. |last14=Yang |first14=Y. |last15=Liu |first15=L. |last16=Xu |first16=G. S. |last17=Zang |first17=Q. |last18=Zhao |first18=H. L. |last19=Peysson |first19=Y. |last20=Decker |first20=J. |last21=Goniche |first21=M. |last22=Cesario |first22=R. |last23=Amicucci |first23=L. |last24=Tuccillo |first24=A. A. |last25=Baek |first25=G. S. |last26=Parker |first26=R. |last27=Bonoli |first27=P. T. |last28=Yang |first28=C. |last29=Zhao |first29=Y. P. |last30=Qian |first30=J. P. |journal=Radio Frequency Power in Plasmas |issue=1 |display-authors=1 }}

EAST was designed to test:

  • Superconducting Niobium-titanium poloidal field magnets, making it the first tokamak with superconducting toroidal and poloidal magnets
  • Non-inductive current drive
  • Pulses of up to 102 seconds with 0.5 MA plasma current
  • Schemes for controlling plasma instabilities through real-time diagnostics
  • Materials for diverters and plasma facing components
  • Operation with βN = 2 and confinement factor H89 > 2

Tokamak parameters

class="wikitable"

|+Tokamak parameters{{cite web|url=http://english.hf.cas.cn/ic/ip/east/|title=EAST (HT-7U Super conducting Tokamak)----Hefei Institutes of Physical Science, The Chinese Academy of Sciences}}

Toroidal field, Bt3.5 T
Plasma current, IP1.0 MA
Major radius, R01.85 m
Minor radius, a0.45 m
Aspect ratio, R/a4.11
Elongation, κ1.6–2
Triangularity, δ0.6–0.8  
Ion cyclotron resonance heating (ICRH)3 MW
Lower hybrid current drive (LHCD)4 MW
Electron cyclotron resonance heating (ECRH)None currently (0.5 MW planned)
Neutral beam injection (NBI)None currently (planned)
Pulse length1–1000 s
ConfigurationDouble-null divertor
Pump limiter
Single null divertor

See also

References

{{reflist|33em}}