T-15 (reactor)

Last updated
T-15
Tokamak-15
1987 CPA 5891.jpg
T-15 tokamak on a 1987 USSR stamp [1]
Device type Tokamak
Location Moscow, Russia
Affiliation Kurchatov Institute
Technical specifications
Major radius2.43 m (8 ft 0 in)
Minor radius0.7 m (2 ft 4 in)
Plasma volume50  m3
Magnetic field 3.6 T (36,000 G)
Heating power3  MW
History
Year(s) of operation1988–1995
Succeeded byT-15MD

The T-15 (or Tokamak-15) is a Russian (previously Soviet) nuclear fusion research reactor located at the Kurchatov Institute, which is based on the (Soviet-invented) tokamak design. [2] It was the first industrial prototype fusion reactor to use superconducting magnets to control the plasma. [3] These enormous superconducting magnets confined the plasma the reactor produced, but failed to sustain it for more than just a few seconds. Despite not being immediately applicable, this new technological advancement proved to the USSR that they were on the right path. In the original (circular cross-section with limiter) shape, a toroidal chamber design, it had a major radius of 2.43 m and minor radius 0.7 m. [4]

Contents

The T-15 achieved creating its first thermonuclear plasma in 1988 and the reactor remained operational until 1995. The plasma created was thought to solve a number of issues engineers have struggled with in the past.[ clarification needed ][ citation needed ] This combined with the USSR's desire for cheaper energy ensured the continuing progress of the T-15 under Mikhail S. Gorbachev. It was designed to replace the country's use of gas and coal as the primary sources of energy.

It achieved 1 MA and 1.5 MW injection for 1 second pulse. [5] It carried out about 100 shots before closing (in 1995) due to a lack of funds. [6]

1996 upgrade

From 1996 to 1998 a series of upgrades were made to the reactor, in order to conduct preliminary research for the design work on the International Thermonuclear Experimental Reactor or ITER. One of the upgrades converted the tokamak to a D-shape divertor design with a major plasma radius of 1.5 m. ITER will also use superconducting magnets. The nuclear predecessors before such as the T-10 were capable of reaching 16.7 MK plasma temperature. This increased temperature made it possible to introduce the electron cyclotron resonance (ECR), ion cyclotron resonance (ICR), and neutral atoms, as to maintain the reactions.[ citation needed ]

Upgrade to T-15MD

T-15MD vacuum vessel shell T-15MD Vacuum vessel shell.jpg
T-15MD vacuum vessel shell
T-15MD toroidal winding and poloidal field coils after disassembly T-15 Toroidal winding and poloidal field coils.jpg
T-15MD toroidal winding and poloidal field coils after disassembly

In the year 2010 it was decided to upgrade the reactor. [7] The upgraded machine is called T-15MD. On the basis of the T-15 there will be created a nuclear fusion–fission hybrid reactor, intended to use the neutrons generated by a core fusion reactor component to incite fission in otherwise nonfissile fuels, and to explore the feasibility of such a system for power generation. [8] [9] Assembly of the magnetic coils was finished in August 2019. [10] As of early 2020 the status of construction was reported as "entering the final phase". [11] At the end of 2020, preparations for the physical start-up of T-15MD were completed. [10] The physical launch took place in May 2021 and further hardware upgrades are planned until 2024. [12]

T-15MD has a major radius R = 1.48 m and a minor radius a = 0.67 m. The toroidal magnetic field is 2 T, produced by ordinary conducting coils. The intended plasma current is 2 MA, which is planned to be sustained for 40 s with neutral particle injection and microwaves, and without using inductive current drive. [13]

Related Research Articles

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JT-60 is a large research tokamak, the flagship of the Japanese National Institute for Quantum Science and Technology's fusion energy directorate. As of 2023 the device is known as JT-60SA and is the largest operational superconducting tokamak in the world, built and operated jointly by the European Union and Japan in Naka, Ibaraki Prefecture. SA stands for super advanced tokamak, including a D-shaped plasma cross-section, superconducting coils, and active feedback control.

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References

  1. "The second life of Tokamak T-15". www.iter.org. 5 November 2010. Archived from the original on 28 June 2017.
  2. "Russian Research Centre "Kurchatov Institute"". 2005-02-25. Archived from the original on 2005-02-25. Retrieved 2020-06-20.
  3. Smirnov, V.P. (2010). "Tokamak foundation in USSR/Russia 1950–1990" (PDF). Nuclear Fusion. 50 (1): 014003. Bibcode:2010NucFu..50a4003S. CiteSeerX   10.1.1.361.8023 . doi:10.1088/0029-5515/50/1/014003. ISSN   0029-5515. S2CID   17487157.
  4. Belyakov, V. P.; Glukhikh, V. A.; Kavun, A. M.; Kadomtsev, B. B.; Kovalenko, V. D.; Kostenko, A. I.; Malyshev, I. F.; Monoszon, N. A.; Popkov, G. N.; Stavisskii, B. A.; Strelkov, V. S. (1982). "The T-15 tokamak. Basic characteristics and research program". Soviet Atomic Energy. 52 (2): 103–111. doi:10.1007/BF01138918.
  5. "Superconducting Tokamak T-15 Upgrade. Kirnev et al" (PDF). Archived from the original (PDF) on 2014-08-11. Retrieved 2014-08-07.
  6. The Second Life of Tokamak T-15, Iter newsline, 5 November 2010
  7. TOKAMAK T-15MD: experience of scientific and technical project realization in RUSSIA (2017)
  8. Upgraded Russian tokamak T-15 launch in 2018
  9. Пуск модернизированной российской термоядерной установки ожидается в 2018 году
  10. 1 2 Petr Khvostenko. "Tokamak T-15MD – preparing for physical start-up". 28th IAEA Fusion Energy Conference.
  11. Khvostenko, P. P. (2020). "Preparation to physical start up of tokamak T-15MD has reached the final stage" (PDF).
  12. "Russia launches T-15MD tokamak at the Kurchatov Institute". Nuclear Engineering International. 2021-05-20.
  13. Litvak, A.G.; Romannikov, Alexander (2017). "Medium size tokamak T-15MD as a base for experimental fusion research in Russian Federation". EPJ Web of Conferences. 149: 01007. Bibcode:2017EPJWC.14901007R. doi: 10.1051/epjconf/201714901007 . ISSN   2100-014X.

Further reading

55°48′05″N37°28′37″E / 55.8014°N 37.4769°E / 55.8014; 37.4769