 | This article may rely excessively on sources too closely associated with the subject , potentially preventing the article from being verifiable and neutral.(April 2015) |
The Plasma Physics Laboratory at the University of Saskatchewan was established in 1959 by H. M. Skarsgard. Early work centered on research with a Betatron.
STOR-1M is Canada's first tokamak built in 1983. In 1987 STOR-1M was the world’s first demonstration of alternating current in a tokamak. [1] [2]
| Saskatchewan Torus-Modified | |
|---|---|
| Device type | Tokamak |
| Location | Saskatchewan, Canada |
| Affiliation | University of Saskatchewan |
| Technical specifications | |
| Major radius | 46 cm (18 in) |
| Minor radius | 12.5 cm (4.9 in) |
| Magnetic field | 0.5–1 T (5,000–10,000 G) |
| Plasma current | 30–60 kA |
| History | |
| Year(s) of operation | 1987–present |
| Preceded by | STOR-1M |
STOR-M stands for Saskatchewan Torus-Modified. STOR-M is a tokamak located at the University of Saskatchewan. STOR-M is a small tokamak (major radius = 46 cm, minor radius = 12.5 cm) designed for studying plasma heating, anomalous transport and developing novel tokamak operation modes and advanced diagnostics. STOR-M is capable of a 30–40 millisecond plasma discharge with a toroidal magnetic field of between 0.5 and 1 tesla and a plasma current of between 20 and 50 kiloamperes. STOR-M has also demonstrated improved confinement induced by a turbulent heating pulse, electrode biasing and compact torus injection.
A stellarator is a plasma device that relies primarily on external magnets to confine a plasma. Scientists researching magnetic confinement fusion aim to use stellarator devices as a vessel for nuclear fusion reactions. The name refers to the possibility of harnessing the power source of the stars, such as the Sun. It is one of the earliest fusion power devices, along with the z-pinch and magnetic mirror.
A tokamak is a device which uses a powerful magnetic field to confine plasma in the shape of a torus. The tokamak is one of several types of magnetic confinement devices being developed to produce controlled thermonuclear fusion power. As of 2016, it was the leading candidate for a practical fusion reactor.
Princeton Plasma Physics Laboratory (PPPL) is a United States Department of Energy national laboratory for plasma physics and nuclear fusion science. Its primary mission is research into and development of fusion as an energy source. It is known in particular for the development of the stellarator and tokamak designs, along with numerous fundamental advances in plasma physics and the exploration of many other plasma confinement concepts.
The Joint European Torus, or JET, is an operational magnetically confined plasma physics experiment, located at Culham Centre for Fusion Energy in Oxfordshire, UK. Based on a tokamak design, the fusion research facility is a joint European project with a main purpose of opening the way to future nuclear fusion grid energy. At the design stage JET was larger than any such machine then in production.
The Large Helical Device (LHD) is a fusion research device in Toki, Gifu, Japan, belonging to the National Institute for Fusion Science. It is the second largest superconducting stellarator in the world, after the Wendelstein 7-X. The LHD employs a heliotron magnetic field originally developed in Japan.
A spheromak is an arrangement of plasma formed into a toroidal shape similar to a smoke ring. The spheromak contains large internal electric currents and their associated magnetic fields arranged so the magnetohydrodynamic forces within the spheromak are nearly balanced, resulting in long-lived (microsecond) confinement times without external fields. Spheromaks belong to a type of plasma configuration referred to as the compact toroids.
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 Enormous Toroidal Plasma Device (ETPD) is an experimental physics device housed at the Basic Plasma Science Facility at University of California, Los Angeles (UCLA). It previously operated as the Electric Tokamak (ET) between 1999 and 2006 and was noted for being the world's largest tokamak before being decommissioned due to the lack of support and funding. The machine was renamed to ETPD in 2009. At present, the machine is undergoing upgrades to be re-purposed into a general laboratory for experimental plasma physics research.
ASDEX Upgrade is a divertor tokamak, that went into operation at the Max-Planck-Institut für Plasmaphysik, Garching in 1991. At present, it is Germany's second largest fusion experiment after stellarator Wendelstein 7-X.
The Tokamak à configuration variable is a Swiss research fusion reactor of the École Polytechnique Fédérale de Lausanne (EPFL). As the largest experimental facility of the Swiss Plasma Center, the TCV Tokamak explores the physics of nuclear fusion by magnetic confinement. Its distinguishing feature over other tokamaks is that its torus section is three times higher than wide. This allows studying several shapes of plasmas, which is particularly relevant since the shape of the plasma has links to the performance of the reactor. This asset has earned its choice as one of the three national machines in Europe involved in the design of the international reactor ITER, as well as in the development of ITER’s successor DEMO, a prototype of a commercial reactor. The TCV was set up in November 1992.
WEST, 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.
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 with a cored apple. The spherical tokamak is sometimes referred to as a spherical torus and often shortened to ST.
The GLAss Spherical Tokamak is a name given to a set of small spherical tokamaks located in Islamabad, Pakistan. They were developed by the Pakistan Atomic Energy Commission (PAEC) as part of the National Tokamak Fusion Program (NTFP) in 2008 and are primarily used for teaching and training purposes.
The ISTTOK Tokamak is a research fusion reactor (tokamak) of the Instituto Superior Técnico. It has a circular cross-section due to a poloidal graphite limiter and an iron core transformer. Its particularity is that it is one of the few tokamaks operating in AC regime, as well in DC regime. In 2013, the AC operation allowed the standard discharges to extend from 35 ms to more than 1s.
The Spherical Tokamak Experiment is a machine dedicated to plasma studies in low aspect ratio tokamaks. The ETE was entirely designed and assembled at the Associated Plasma Laboratory of Brazil's National Institute for Space Research (INPE).
COMPASS, short for Compact Assembly, is a compact tokamak fusion energy device originally completed at the Culham Science Centre in 1989, upgraded in 1992, and operated until 2002. It was designed as a flexible research facility dedicated mostly to plasma physics studies in circular and D-shaped plasmas.
Robert James Goldston is a professor of astrophysics at Princeton University and a former director of the Princeton Plasma Physics Laboratory.
High-confinement mode, or H-mode, is an operating mode possible in toroidal magnetic confinement fusion devices – mostly tokamaks, but also in stellarators. In this mode the plasma is more stable and better confined.
The Prairie View (PV) Rotamak is a plasma physics experiment at Prairie View A&M University. The experiment studies magnetic plasma confinement to support controlled nuclear fusion experiments. Specifically, the PV Rotamak can be used as either a spherical tokamak or a field-reversed configuration. Some time between 2015 and 2017, all personnel left the project, leaving it vacant.
The Compact Toroidal Hybrid (CTH) is an experimental device at Auburn University that uses magnetic fields to confine high-temperature plasmas. CTH is a torsatron type of stellarator with an external, continuously wound helical coil that generates the bulk of the magnetic field for containing a plasma.
Fusion power, processes and devices | |||||||||||||||||||||||||||||||||||||||||||
|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|---|
| Core topics | |||||||||||||||||||||||||||||||||||||||||||
| Processes, methods |
| ||||||||||||||||||||||||||||||||||||||||||
| Devices, experiments |
| ||||||||||||||||||||||||||||||||||||||||||
 | This Saskatchewan-related article is a stub. You can help Wikipedia by expanding it. |
 | This article about an organization or institute connected with physics is a stub. You can help Wikipedia by expanding it. |
 | This plasma physics–related article is a stub. You can help Wikipedia by expanding it. |
