No abstract available

[en] The computer code, ground rules, and plasma scalings used in the trade studies are briefly discussed. The results of these analyses are presented in detail. The results are summarized and pertinent conclusions and recommendations regarding the TNS design options are discussed

No abstract available

No abstract available

[en] The results of an extensive set of parametric studies are presented which provide analytical data of the effects of various tokamak parameters on the performance and cost of the DTHR (Demonstration Tokamak Hybrid Reactor). The studies were centered on a point design which is described in detail. Variations in the device size, neutron wall loading, and plasma aspect ratio are presented, and the effects on direct hardware costs, fissile fuel production (breeding), fusion power production, electrical power consumption, and thermal power production are shown graphically. The studies considered both ignition and beam-driven operations of DTHR and yielded results based on two empirical scaling laws presently used in reactor studies. Sensitivity studies were also made for variations in the following key parameters: the plasma elongation, the minor radius, the TF coil peak field, the neutral beam injection power, and the Z/sub eff/ of the plasma

No abstract available

[en] This report presents results from studies of the radiation environment expected in and around the Tokamak Fusion Test Reactor (TFTR) Facility. The TFTR is scheduled for operation by 1981 and will be located on the Princeton Forrestal Campus. The conceptual design and planned operation of the TFTR device and facility have been significantly affected by the anticipated production of neutrons and gamma rays during the pulsing of the device with deuterium or deuterium-tritium fuel. It is expected that reactor grade plasmas having fusion power densities >1 W/cm³ will be generated, and that many of the associated engineering problems which are typical of those to be encountered in future power producing fusion reactors will be addressed. On the other hand, in view of the experimental nature of the device, the number of deuterium-tritium pulses will be limited so that stifling radiation effects will not be encountered. The radiation analyses used for the TFTR conceptual design are described in this report. Presentations are given of the: (1) analytical methods and their application to the design of the radiation shielding, (2) composition, dimensions, and arrangement of the device shielding and of the walls of the facility, (3) modes of operation and the associated radiation environments, (4) neutron activations of the device auxiliary components, cooling water, and Test Cell air as a function of irradiation history and time after shutdown, (5) radiation levels throughout the facility and site out to the site boundary

[en] A computer code, W-COPE, has been developed to carry out analyses of the Ohmic Heating Coil (OH) and Equilibrium Field Coil (EF) circuits and to scope the required circuit components for the Tokamak Fusion Test Reactor (TFTR). The model which has been formulated has the capability of determining the energy and power requirements of the OH and EF circuits for plasma initiation, maintenance, and compression. For the compression model it is possible to independently force the EF circuit and determine the OH voltage and current requirements to compress without initiating ''skin currents'' in the plasma. The TFTR circuitry as modeled and coded in W-COPE is presented with a description of the scheduled or resultant behavior of various system components both during precompression and compression of the plasma; input constants used in analyses, e.g., resistances and inductances, are given; and the results of typical analyses are also presented and discussed. The energy-storage capacity of the condensers and the ratings of the power supplies required for the conceptual design of the EF and OH circuits for the TFTR are given

[en] The ORNL/Westinghouse program for The Next Step (TNS) tokamak beyond TFTR has examined a large number of potential configurations for D-T burning ignition tokamak systems. An objective of this work has been to quantify the trade-offs associated with the assumption of certain plasma physics criteria and toroidal field coil technologies. Four tokamak system point designs are described, each representative of the TF coil technologies considered, to illustrate the engineering features associated with each concept. Point designs, such as the ones discussed herein, have been used to develop component size, performance and cost scaling relationships which have been incorporated in a digital computer code to facilitate an examination of the total design and cost impact of candidate design approaches. The point designs which are described are typical, however, they have not been individually optimized. The options are distinguished by the TF coil technology chosen and include: (1) a high field water-cooled copper TF system, (2) a moderate field NbTi superconducting TF system, (3) a high field Nb₃Sn superconducting TF system, and (4) a high field hybrid TF system with outer NbTi superconducting windings and inner water-cooled copper windings. Descriptions are provided for the major device components and all major support systems including power supplies, vacuum systems, fuel systems, heat transport and facility systems

[en] A series of parametric trade studies was performed to consistently evaluate the relative costs and performance parameters of D-T burning tokamaks over a range of plasma sizes and toroidal field (TF) coil technologies. Four different types of TF coil technologies were investigated: water-cooled copper coils, superconducting NbTi and Nb₃Sn coils, and a ''hybrid'' coil arrangement consisting of a normal conducting Cu coil nested within a superconducting NbTi coil. Results of the analysis indicate for TNS operation, for example, that for a given plasma beta at ignition, the Cu TF coil devices are least expensive, followed by the Nb₃Sn, NbTi, and NbTi/Cu options. Other conclusions and trends resulting from the study are presented and analyzed