[en] TFTR is a second generation tokamak whose key objective is scientific break-even. TFTR is expected to be the first machine to demonstrate proper combination of plasma confinement time, density, and temperature to obtain this objective. A summary of major TFTR design parameters, including TFM, is presented, and their potential impact on future tokamaks discussed. Details of the updated engineering design and analysis of components are described. Status of major hardware fabrication, assembly installation and test are reviewed. TFTR features, technology, predicted performance and their potential implication for future tokamaks are summarized

[en] Progress with the Tokamak Fusion Test Reactor (TFTR) at Princeton University's Plasma Physics Laboratory is reviewed. Experiments planned for 1983 are described. The machine is compared with the Joint European Torus (JET). (U.K.)

[en] The toroidal field coils for the TFTR Project are relatively large circular coils wound with hollow copper conductor. Sections of conductor lengths are brazed together, insulated, then wound around a circular mandrel. The completed coil must fit into a machined metallic case making the configuration control of the insulated coil very important during winding. The approach to the winding of these coils, a brief description of some of the winding tooling, and methods employed to wind the TFTR TF coils are discussed here

[en] This engineering treatment considers transformer configuration, design, materials, and quality control

[en] Overall the Area Safety Program has proved to be a very successful operation. There is no doubt that a safety program organized through line management is the best way to involve all personnel. Naturally, when the program was first started, there was some criticism and a certain resistance on the part of a few individuals to fully participate. However, once the program was underway and it could be seen that it was working to everyone's advantage, this reluctance disappeared and a spirit of full cooperation is now enjoyed. It is very important that for this success to continue there must be a two way flow of information, both from the Area Safety Coordinators up through line management, and from senior management, with decisions and answers, back down through the management chain with the utmost dispatch. As with all programs, there is still room for improvement. This program has started a review cycle with a view to streamlining certain areas and possibly increasing its scope in others

[en] The Tokamak Fusion Test Reactor (TFTR) is a large fusion device being constructed at the Plasma Physics Laboratory of Princeton University. This unit is designed for bakeout at 250 ₀C, and for a base pressure of 10^-₈ Torr. The machine has a total of 57 large ports that are removable and are sealed with ''Helicoflex'' metallic gaskets. There are two seals on each port, a primary and a secondary, with flange bolts between seals. This arrangement balances the load on either side of the bolts, eliminating flange roll that could result from the high sealing forces. The dual seal arrangement also aids in leak detection and permits recovery from a failed primary seal by pumping between seals. All of the large ports have been leak-checked with a helium mass spectrometer leak detector, and all primary seals have been found to be leak tight

[en] The final design of the TF coil subassemblies includes iterations which gave consideration to improvement of coil reliability while minimizing potential fabrication difficulties. A pre-production qualification program was implemented to develop and verify key production processes and parameters. The manufacturing plan employs the techniques, materials, methods and procedures necessary to fabricate coils which meet or exceed the design criteria. This paper highlights those design changes and results of the qualification program and outlines the manufacturing plan. 4 refs

[en] Princeton had to implement extensive modifications in the present buildings to set up facilities which could accommodate tooling and manufacture of the largest coils ever developed for fusion research. A description is given of the manufacturing steps necessary to produce the TFTR, PF Coils ranging from 16 to 33 feet in diameter and weighing up to 25,000 lbs

[en] This report is a thorough scientific review of the TFTR physics situation. This review was intended to provide a reference point from which to develop future ETM policy toward the Engineering Test Facility (ETF) development program and to define possible modifications to the TFTR program to better support the ETF

[en] Wall power deposition and erosion rates due to charge-exchanging neutrals, along with pumping rates, are computed for various TFTR and INTOR/FED limiter and divertor schemes. It was found that only approx. equal to 7% of charge exchange power was deposited on the first wall in a proposed INTOR/FED 'T' limiter. Thus, the first wall will not have to be replaced as often as the limiter. (orig.)