| Term | Definition |
|---|---|
| T-15 | Tokamak-15, an experiment at the Kurchatov Institute, Russian Federation |
| TBC | to be confirmed |
| TBD | to be determined |
| TCV | Tokamak à Configuration Variable, an experiment at CRPP Lausanne, Switzerland. |
| teaching-playback procedure | A procedure usually used with remote handling systems whereby operations are carried out using automatic equipment under manual control, and the actions are recorded to be carried out in future under automatic control after initial setup. Similar to the creation of a macro on a computer. |
| technical specifications and drawings | Drawings and specifications consistent with the procurement plan and providing the necessary level of detail to support the procurement process. |
| TEXTOR-94 | An experiment at Forschungszentrum Jülich, Germany, engaged in the study of plasma wall interactions. |
| TF | toroidal field |
| TF insert | An insert coil placed in the bore of the CS model coil test facility and made from prototypical conductor for the ITER TF coils. |
| TF ripple | Because a discrete number of toroidal field coils are used in ITER, the toroidal field experienced towards the outboard side of the plasma fluctuates in value at a given radius from the vertical machine centreline, being higher at a given radius in the shadow of each coil than between the coils. This “ripple” in the field traps particles and provides a mechanism for power loss. Thus maintaining a low ripple is a priority. In ITER, ferromagnetic material inserts are placed in the shadow of the TF coils, as these weaken the ripple. |
| TFTR | Tokamak Fusion Test Reactor, a now decommissioned plasma experiment located in Princeton, USA |
| thermal energy | Energy due to the relatively high temperature of a medium relative to its surroundings. |
| thermal loads | Heat loads experienced by a body. |
| thermal plasma | A plasma in which the vast majority of collisions occur due to random rather than directed impact (e.g. due to a beam of incoming particles). In this case the plasma particles adopt a Maxwellian distribution of velocities and the energy content of the plasma is thus determined by the plasma temperature. |
| thermo-hydraulic load | The combined load from the pressure of the coolant and the heat source, such as experienced by the plasma-facing components of ITER. |
| thermonuclear fusion | Fusion at high temperature with a significant release of energy. |
| thixotropy | The propery of certain gels of becoming fluid when agitated and of reverting back to a gel when left to stand. |
| threshold power | If the power input to afusion fuel plasma exceeds a certain level then a high enough temperature is reached that heating from fusion reactions plus the external power exceeds the power lost by radiation and conduction, and the plasma temperature continues to rise. If this threshold is not reached then the temperature does not rise despite continued external heating. |
| TIG welding | Tungsten inert gap welding. |
| tokamak | (toroidalnaya kamera + magnitnaya katushka), a device for containing a plasma inside a torus chamber by using a combination of two magnetic fields--one created by electric coils around the torus, the other created by intense electric current in the plasma itself. |
| tokamak building | The main building housing the tokamak and its main peripheral equipment. |
| TORE-SUPRA | A fusion experiment at Cadarache, France, using superconducting coils and aimed particularly at demonstrating long pulse tokamak operation. |
| toroidal Alfvén eigenmode | TAE, a branch of magnetohydrodynamic instabilities associated with Alfvén waves propagating in the toroidal direction. |
| toroidal direction | In a ring doughnut, the direction parallel to the large circumference. |
| toroidal field | TF, a magnetic field generated by a currrent flowing in a solenoid around a torus. |
| toroidal field coils |
TF coils, these coils confine a plasma by creating a magnetic bottle for confinement. |
| toroidal magnetic field on axis | The magnetic field at the centre of the plasma. |
| toroidal system | Name given to the general class of "doughnut-shaped" magnetic devices in which magnetic lines of force closing in on themselves. Stellarators and tokamaks are examples. |
| toroidal vessel | A torus-shaped chamber used to confine plasma. |
| torus | A magnetic component (a coil or a transformer) made in the shape of an anchor ring. With this construction, most of the magnetic field is contained within the core and leakage is minimal. Thus, there is little or no interaction with adjacent components and circuits. Also toroid. |
| TOSKA facility | Torus Spulen Testanlage Karlsruhe, a facility of Forschungszentrum Karlsruhe, Germany, used for superconducting coil testing and in which the TF model coil for ITER was tested. |
| Townsend avalanche | (Phys.) A cumulative ionization process in which the ions and electrons of one generation undergo collisions that produce a greater number of ions and electrons in succeeding generations. |
| transferred arc |
(Met) In plasma arc welding, an arc established between the electrode and the workpiece. |
| transport | The rate at which desired material is carried through any section of a processing plant, e.g. isotopes in isotope separation. |
| transport matrix coefficient | The coefficient which defines various physical processes in a plasma. |
| triangularity | The amount of inward asymmetry in a noncircular-shaped plasma. |
| triple product | The confinement time, density, and temperature product used to characterize the quality of confinement. |
| tritiated | Referring to any material or system that has become contaminated or infused with tritium. |
| tritium | The third isotope of hydrogen, containing one proton and two neutrons in the nucleus. |
| tritium breeding ratio | TBR, the time-averaged value of the ratio of the tritium produced in the blanket surrounding the plasma in ITER, or in future fusion devices, divided by the tritium consumed in the plasma (or decaying by natural radioactive decay). Sometimes a “local” tritium breeding ratio is defined, representing the value of the global TBR which would be achieved if applied across the whole plasma surface (taking account of geometrical neutron flux variations). |
| tritium building | The building adjacent to the tokamak building which houses the tritum plant. |
| tritium handling | The processes of tritium removal from gas streams, including plasma exhaust and the plant atmosphere, and returning it to use as fuel in the plasma or to storage, in a safe manner. See tritium plant. |
| tritium plant | Any plant which involves tritium in significant quantities. For ITER, it is a facility which receives, stores, recycles, purifies and extracts tritium from the tokamak fuelling system and other processes which become tritiated. |
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