The document also contains discussions of systems integration and assembly, key research and development needs, and schedule considerations. Tritium processing, tritium containment and vacuum systems employ double containment and atmospheric cleanup to minimize releases. The rate of field change imposed upon the toroidal field coils is reduced by at least a factor of 3.3 compared to that due to the plasma alone. The poloidal magnetics system is specially designed both to reduce the total volt-second energy requirements and to reduce the magnitude of the rate of field change at the toroidal field coils. The structural system uses a stainless steel center bucking ring and intercoil box beam bracing to provide rigid support for coils against the centering force, overturning moments from poloidal fields and faults, other external forces, and thermal stresses. The coil system was developed for a maximum field of 11 T at the winding (to give a field on axis of 4.8 T), and combines multifilamentary superconducting cable with forced flow of supercritical helium enclosed in a steel conduit. Nb$sub 3$Sn and NbTi superconductors are used in the toroidal field coil design. Neutronics and heat transfer calculations coupled with mechanical design and materials considerations were used to develop a blanket and shield capable of operating at high temperature, protecting the more » surrounding coils, being maintained remotely and, in a few experimental modules, breeding tritium. The set of basic plasma parameters selected-minor radius of 2.25 m, major radius of 6.75 m, magnetic field on axis of 4.8 T and plasma current of 7.2 MA-should produce a reactor-grade plasma with a significant neutron flux, even with the great uncertainty in plasma physics scaling from present experience to large sizes. « lessĪ Tokamak EPR Reference Design is presented as a basis for further design study leading to a Conceptual Design. The circular design, however, is less sensitive to magnetic field perturbations which may be encountered in proof testing. Further, the oval TF coil shape in its present design has a significant safety margin between working and yield stress under normal operating conditions. Based upon the preceding conditions the oval TF coil shape appears to be superior to the circular TF coil shape. The scope of the analysis covers only the in-plane force distribution produced by the magnetic field. The study is a part of the joint U.S.A./U.S.S.R. This study reports the results of a cooperative investigation to determine which TF coil shape operates in a minimum stress configuration. Either geometry produces a magnetic field of 3.5 T on axis, 2.4 m from the machine center line. The cross sections of both TF coil shapes have rectangular dimensions of 0.4 m by 0.26 m with a 0.36-m by 0.22-m winding more » cavity symmetrically placed within the cross section. The circular TF coil system has a 2.5-m major radius with a 2.2-m bore diameter. The oval TF coil system has a 2.4-m major radius with a minor bore diameter of 2.15 m and a major bore diameter of 3.28 m. Each TF coil system is composed of 24 coils. Two TF coil shapes were proposed, one oval and the other circular. A structural analysis of the T-10M tokamak toroidal field (TF) coil system has been performed.
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