- Art Gallery -

The Small Tight Aspect Ratio Tokamak, or START was a nuclear fusion experiment that used magnetic confinement to hold plasma. START was the first full-sized machine to use the spherical tokamak design, which aimed to greatly reduce the aspect ratio of the traditional tokamak design.

The experiment began at the Culham Science Centre in the United Kingdom in 1990 and was retired in 1998. It was built as a low cost design, largely using parts already available to the START team. The START experiment revolutionized the tokamak by changing the previous toroidal shape into a tighter, almost spherical, doughnut shape. The new shape increased efficiency by reducing the cost over the conventional design, while the field required to maintain a stable plasma was a factor of 10 less.

The main components that comprised START included the support structure, pulse transformer, vacuum tank, toroidal and poloidal field coils, and a limiter. The support structure positioned and supported the vacuum tank which also shared the same spherical center as the large pulse transformer. The main role of the pulse transformer was to provide the current for the toroidal field coils which was supplied through fifteen irons cores that were spirally wound from a .03 millimeter iron strip. The toroidal field coil was a central conductor made of copper on the axis of the vacuum tank, and was attached to the vacuum tank through copper limbs covered by insulated clamps. START had six poloidal field coils within the vacuum tank and were encased in 3 millimeter stainless steel cases. The poloidal coils were supported from the base of the tank and each could be adjusted as necessary. The vacuum tank was the primary vessel where experiments take place; it was cylindrical in shape and was divided into three sections. The tank offered numerous ports for the attachment of pumps and diagnostics. A graphite limiter was positioned around the central stainless steel tube and this provided a simple way to measure the innermost edge of the plasma during experiments.[1]

In order to successfully heat experiments in a spherical tokamak, physicists performed neutral beam injection. This involved interjecting hydrogen into hydrogen or deuterium plasmas, providing effective heating of both ions and electrons. Although the atoms were injected with no net electrostatic charge, as the beam passed through the plasma, the atoms were ionized as they bounced off the ions already in the plasma. Consequently, because the magnetic field inside the torus was circular, these fast ions were confined to the background plasma. The background plasma slowed the confined fast ions, in a similar way to how air resistance slows down a baseball. The energy transfer from the fast ions to the plasma increased the overall plasma temperature. The neutral beam injector used in START was on loan from Oak Ridge National Laboratory.[2]

The magneto-hydro-dynamic limit (MHD) was an operational limit of tokamaks, with START being no exception. The START team would test the MHD using forty-six sets of Mirnov coils at different heights on the center column of START. Plasmas being formed by compression within START limited the fluctuation of the MHD.[3]

Prior to October 1995, START had no rapid terminations. In October 1995, divertor coils were installed and images showed the plasma would interact with the coils before disruptions occurred. These suspicions were further strengthened when the divertor coils were moved closer to the plasma in December 1996, which resulted in a higher frequency of disruptions.[3]

The characteristics of plasma within START were also measured. Typical plasma within START had an aspect ratio A=1.3, elongation k=1.8, and a temperature of 400 eV.[2][4]

A number of experiments reached 32 percent beta with START, where the previous world record for beta in a tokamak was 12.6 percent. Factors that contributed to the significantly higher beta number include better vacuum conditions, a more powerful neutral beam injection, a lower toroidal field, a higher plasma pressure, and a lower magnetic pressure.[4]

In March 1998, the START experiment finished and has since been disassembled and transferred to the ENEA research laboratory at Frascati, Italy. The START team began the Mega Ampere Spherical Tokamak Experiment or MAST in 1999 which operated in the Culham Science Centre, UK until 2013.

Smith, R.T.C, et al. "Design of the START Experiment." Proceedings- Symposium of Fusion Engineering 2 (1989): 866-68. Web. 2 Nov. 2014.
Sykes, Alan, and R.J. La Haye. "High Beta Produced By Neutral Beam Injection In The START (Small Tight Aspect Ratio Tokamak).." Physics Of Plasmas 4.5 (1997): 1665. Academic Search Premier. Web. 30 Oct. 2014.
Hender, T. C., et al. "Magneto-Hydro-Dynamic Limits In Spherical Tokamaks." Physics Of Plasmas 6.5 (1999): 1958. Academic Search Premier. Web. 31 Oct. 2014.
Gates, D.A., and R. Akers. "High-Performance Discharges In The Small Tight Aspect Ratio Tokamak (START)." Physics Of Plasmas 5.5 (1998): 1775. Academic Search Premier. Web. 30 Oct. 2014.


Fusion power, processes and devices
Core topics

Nuclear fusion
Timeline List of experiments Nuclear power Nuclear reactor Atomic nucleus Fusion energy gain factor Lawson criterion Magnetohydrodynamics Neutron Plasma


Alpha process Triple-alpha process CNO cycle Fusor Helium flash Nova
remnants Proton-proton chain Carbon-burning Lithium burning Neon-burning Oxygen-burning Silicon-burning R-process S-process


Dense plasma focus Field-reversed configuration Levitated dipole Magnetic mirror
Bumpy torus Reversed field pinch Spheromak Stellarator Tokamak
Spherical Z-pinch


Bubble (acoustic) Laser-driven Magnetized Liner Inertial Fusion


Fusor Polywell

Other forms

Colliding beam Magnetized target Migma Muon-catalyzed Pyroelectric

Devices, experiments
Magnetic confinement




Canada STOR-M United States Alcator C-Mod ARC
SPARC DIII-D Electric Tokamak LTX NSTX
PLT TFTR Pegasus Brazil ETE Mexico Novillo [es]


HT-7 SUNIST India ADITYA SST-1 Japan JT-60 QUEST [ja] Pakistan GLAST South Korea KSTAR


European Union JET Czech Republic COMPASS GOLEM [cs] France TFR WEST Germany ASDEX Upgrade TEXTOR Italy FTU IGNITOR Portugal ISTTOK Russia T-15 Switzerland TCV United Kingdom MAST-U START STEP


United States CNT CTH HIDRA HSX Model C NCSX Costa Rica SCR-1


Australia H-1NF Japan Heliotron J LHD


Germany WEGA Wendelstein 7-AS Wendelstein 7-X Spain TJ-II Ukraine Uragan-2M
Uragan-3M [uk]


Italy RFX United States MST

Magnetized target

Canada SPECTOR United States LINUS FRX-L – FRCHX Fusion Engine


Russia GDT United States Astron LDX Lockheed Martin CFR MFTF
TMX Perhapsatron PFRC Riggatron SSPX United Kingdom Sceptre Trisops ZETA

Inertial confinement

United States Argus Cyclops Janus LIFE Long path NIF Nike Nova OMEGA Shiva




European Union HiPER Czech Republic Asterix IV (PALS) France LMJ LULI2000 Russia ISKRA United Kingdom Vulcan


United States PACER Z machine


Thermonuclear weapon
Pure fusion weapon

International Fusion Materials Irradiation Facility ITER Neutral Beam Test Facility

Physics Encyclopedia



Hellenica World - Scientific Library

Retrieved from "http://en.wikipedia.org/"
All text is available under the terms of the GNU Free Documentation License