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(1998). ITER Toroidal Field Model Coil (TFMC) Design and Construction. Fusion Technology: Vol. 34, Proceedings of the Thirteenth Topical Meeting on the Technology of Fusion Energy. Nashville, Tenessee. June 7–11, 1998, pp. 797-801.

The design and operation of a spheromak-like compact toroid (SCT) plasma accelerator is described. As an example application, some principles are presented for using the device as a plasma injector...

Shielding analyses for toroidal field coils (TFCs) around the exhaust duct in a nuclear fusion experimental reactor have been performed by two-dimensional discrete ordinate method, and their peak n...

To improve scheduled and unscheduled maintenance of the nuclear island, methods of supporting the out-of-plane TF loads so as not to interfere with maintenance operation would be highly desirable. Even if the toroidal field coil were extended outwardly to allow for maintenance to toroidally segmented modules, ideally there should not be structures in between coils in the outboard legs of the toroidal field coil. The number of these modules is the same as the number of toroidal field coils, and therefore one and only one module is removed between a pair of adjacent TF coils. Structural analyses of several cases that have the common feature of avoiding material in between the outer legs of the TF coil are presented in this paper. The implications on the structural amount of material required are investigated. 2 refs., 6 figs., 1 tab.

The motivation for this design study has been to identify magnet designs for useful magnetic fusion experiments which minimize capital cost. Some possibly useful novel design features have been identified. 5 refs., 6 figs., 3 tabs.

We investigate experimentally and theoretically the global MHD characteristics of an ultra-low aspect ratio tokamak (ULART). Since the ULART requires a substantially smaller toroidal field current,...

Experiments in Tokamak-15 were performed to study the STFC heating under the quench. The quench was specially caused by current introduction into STFC at the unchanged input helium temperature. The experimental results and simulation data on temperature heating and amount of heat realized in the pancakes under the quench are given. In the experiments was shown that quench occurs in the internal turns of pancakes and estimations of maximal temperature heating corresponds to calculated ones.

The CIT design has evolved recently from a system in which the central solenoid outer boundary interacts with the inner legs of the toroidal field coils for mutual radial support during operation, ...

Phaedrus-T is a moderate sized tokamak with low toroidal field and substantial radio frequency power capabilities. This machine has only recently become operational and full RF power is expected in...

Magnetic divertors have been proven successful in minimizing plasma/wall interactions and in leading to high-confinement regimes in tokamaks. This suggests that similar benefits may occur i...

The analysis of an l = 2 torsatron with a relatively small pitch angle of the helical winding, which requires an additional toroidal field (TF), is presented. The main advantage of this torsatron d...

The present status of modeling toroidal field (TF) ripple loss of fast alphas from tokamaks is summarized. The modeling issues are discussed, and several new aspect of this problem are described, including gyromotion, radial electric field, and sawtoothing. Existing models predict that TF ripple loss of fast alphas will have a low to moderate impact on the design of a tokamak engineering test reactor.

Several preliminary designs have been generated to compare poloidal field (PF) coil set characteristics for comparable limiter and divertor configurations for the Ignition Studies Project. Different coil set locations relative to the toroidal field (TF) coils have been considered. Specifically, configurations have been evaluated with the PF coils entirely external to the TF coils, entirely internal, and combined (hybrid) with all PF coils internal except one.

The TFCX conceptual designs call for the construction of the reactor torus through the use of ''pie-shaped'' segments for mechanical and maintenance considerations. The use of this concept results in hot spots in the inboard section of the torodial field (TF) coils due to neutron and photon streaming through the slots between the segments. This work studies these effects on the nuclear responses in the TF coils and introduces design solutions to reduce the impact on the reactor design.

In this paper we describe a design of an ignition test reactor based on the LITE concept. The main objective of the device is to study key physics issues of ignited plasma operation. LITE-type devices are characterized by toroidal field coils of plate magnet construction. The plates form a continuous structure in the throat of the magnet. The inplane loads are supported by the conductor, while the out-of-plane loads are supported by external frames. The magnet is designed for operation at relatively high stresses and magnetic fields. There is little or no shielding between the vacuum vessel and the magnet. This type of design results in a compact machine.