Tokamak-15 | |
---|---|
Device type | Tokamak |
Location | Moscow, Russia |
Affiliation | Kurchatov Institute |
Technical specifications | |
Major radius | 2.43 m (8 ft 0 in) |
Minor radius | 0.7 m (2 ft 4 in) |
Plasma volume | 50 m3 |
Magnetic field | 3.6 T (36,000 G) |
Heating power | 3 MW |
History | |
Year(s) of operation | 1988–1995 |
Succeeded by | T-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]
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]
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 ]
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]
A tokamak is a device which uses a powerful magnetic field generated by external magnets to confine plasma in the shape of an axially-symmetrical torus. The tokamak is one of several types of magnetic confinement devices being developed to produce controlled thermonuclear fusion power. The tokamak concept is currently one of the leading candidates for a practical fusion reactor.
Fusion power is a proposed form of power generation that would generate electricity by using heat from nuclear fusion reactions. In a fusion process, two lighter atomic nuclei combine to form a heavier nucleus, while releasing energy. Devices designed to harness this energy are known as fusion reactors. Research into fusion reactors began in the 1940s, but as of 2024, no device has reached net power, although net positive reactions have been achieved.
This timeline of nuclear fusion is an incomplete chronological summary of significant events in the study and use of nuclear fusion.
ITER is an international nuclear fusion research and engineering megaproject aimed at creating energy through a fusion process similar to that of the Sun. Upon completion of construction of the main reactor and first plasma, planned for late 2025, it will be the world's largest magnetic confinement plasma physics experiment and the largest experimental tokamak nuclear fusion reactor. It is being built next to the Cadarache facility in southern France. ITER will be the largest of more than 100 fusion reactors built since the 1950s, with ten times the plasma volume of any other tokamak operating today.
A reversed-field pinch (RFP) is a device used to produce and contain near-thermonuclear plasmas. It is a toroidal pinch which uses a unique magnetic field configuration as a scheme to magnetically confine a plasma, primarily to study magnetic confinement fusion. Its magnetic geometry is somewhat different from that of the more common tokamak. As one moves out radially, the portion of the magnetic field pointing toroidally reverses its direction, giving rise to the term reversed field. This configuration can be sustained with comparatively lower fields than that of a tokamak of similar power density. One of the disadvantages of this configuration is that it tends to be more susceptible to non-linear effects and turbulence. This makes it a useful system for studying non-ideal (resistive) magnetohydrodynamics. RFPs are also used in studying astrophysical plasmas, which share many common features.
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.
Magnetic confinement fusion (MCF) is an approach to generate thermonuclear fusion power that uses magnetic fields to confine fusion fuel in the form of a plasma. Magnetic confinement is one of two major branches of controlled fusion research, along with inertial confinement fusion.
The Kurchatov Institute is Russia's leading research and development institution in the field of nuclear energy. It is named after Igor Kurchatov and is located at 1 Kurchatov Square, Moscow.
Alcator C-Mod was a tokamak that operated between 1991 and 2016 at the Massachusetts Institute of Technology (MIT) Plasma Science and Fusion Center (PSFC). Notable for its high toroidal magnetic field, Alcator C-Mod holds the world record for volume averaged plasma pressure in a magnetically confined fusion device. Until its shutdown in 2016, it was one of the major fusion research facilities in the United States.
The Experimental Advanced Superconducting Tokamak (EAST), internal designation HT-7U, is an experimental superconducting tokamak magnetic fusion energy reactor in Hefei, China. The Hefei Institutes of Physical Science is conducting the experiment for the Chinese Academy of Sciences. It has operated since 2006.
The National Spherical Torus Experiment (NSTX) is a magnetic fusion device based on the spherical tokamak concept. It was constructed by the Princeton Plasma Physics Laboratory (PPPL) in collaboration with the Oak Ridge National Laboratory, Columbia University, and the University of Washington at Seattle. It entered service in 1999. In 2012 it was shut down as part of an upgrade program and became NSTX-U, for Upgrade.
The KSTAR is a magnetic fusion device at the Korea Institute of Fusion Energy in Daejeon, South Korea. It is intended to study aspects of magnetic fusion energy that will be pertinent to the ITER fusion project as part of that country's contribution to the ITER effort. The project was approved in 1995, but construction was delayed by the East Asian financial crisis, which weakened the South Korean economy considerably; however, the project's construction phase was completed on September 14, 2007. The first plasma was achieved in June 2008.
WEST, or Tungsten Environment in Steady-state Tokamak, is a French tokamak that originally began operating as Tore Supra after the discontinuation of TFR and of Petula. The original name came from the words torus and superconductor, as Tore Supra was for a long time the only tokamak of this size with superconducting toroidal magnets, allowing the creation of a strong permanent toroidal magnetic field. After a major upgrade to install tungsten walls and a divertor, the tokamak was renamed WEST.
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A spherical tokamak is a type of fusion power device based on the tokamak principle. It is notable for its very narrow profile, or aspect ratio. A traditional tokamak has a toroidal confinement area that gives it an overall shape similar to a donut, complete with a large hole in the middle. The spherical tokamak reduces the size of the hole as much as possible, resulting in a plasma shape that is almost spherical, often compared to a cored apple. The spherical tokamak is sometimes referred to as a spherical torus and often shortened to ST.
The ARC fusion reactor is a design for a compact fusion reactor developed by the Massachusetts Institute of Technology (MIT) Plasma Science and Fusion Center (PSFC). ARC aims to achieve an engineering breakeven of three. The key technical innovation is to use high-temperature superconducting magnets in place of ITER's low-temperature superconducting magnets. The proposed device would be about half the diameter of the ITER reactor and cheaper to build.
Ksenia Aleksandrovna Razumova is a Russian physicist. She graduated from the Physical Faculty of Moscow University in 1955 and took a position at the then called Kurchatov Institute of Atomic Energy in Moscow, then USSR. She defended her Ph.D. in 1966, was Candidate in Physical and Mathematical sciences in 1967, and became Doctor of Sciences in 1984. She is laboratory head at the Institute of Nuclear Fusion, Russian Research Centre Kurchatov Institute. Since the beginning she is actively involved plasma physics in research on the tokamak line of Magnetic confinement fusion.
Natan Aronovich Yavlinsky was a Russian physicist in the former Soviet Union who invented and developed the first working tokamak.
The history of nuclear fusion began early in the 20th century as an inquiry into how stars powered themselves and expanded to incorporate a broad inquiry into the nature of matter and energy, as potential applications expanded to include warfare, energy production and rocket propulsion.