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A study was conducted on the prototype joint sample which was designed and fabricated by the US-party for the International Thermonuclear Experimental Reactor. Requirements for the full-size joint involve the capacity to operate under alternating current background fields at minimal coupling losses. An overview of the design and fabrication effort, with particular emphasis on procedural steps, is presented.

The design and fabrication techniques for the ITER magnets are supported by the ITER Model Coil Program which focuses on component development and performance verification. The key component of the magnet system is the high current capacity (45 - 60 kA), [Nb.sub.3]Sn, cable-in-conduit conductor, which is now being fabricated under a staged development program. The integrated design features and performance of the 13 T Toroidal Field coils and Central Solenoid will be verified in the Model Coil Program. This paper describes the status of the structural and construction features of the model coils and the test facilities for the model coils at JAERI (Naka) and FZK (Karlsruhe).

US participation in the International Thermonuclear Experimental Reactor Organization's Quench Experiment on Long Length program is focused on the development of new quench detection techniques for cable-in-conduit conductors (CICC). To date, the US is developing internal and external sensors that will be installed in the CICCs prior to and after fabrication, respectively, to monitor temperature and pressure changes.

The design of a prototype central solenoid to verify the design principles and manufacturing methods being developed for the construction of full-size superconducting magnets for the International Thermonuclear Experimental Reactor program is reported. The 13-T model coil is currently being designed by a consortium of researchers from Martin Marietta Space Systems Div., Westinghouse Science and Technology Center and the Japanese Atomic Energy Research Institute.

The Tokamak Physics Experiment (TPX) will be the first Tokamak using superconducting magnets for both the poloidal and toroidal field. It is designed for advanced Tokamak physics experiments in steady-state and long-pulse operation. The TPX superconducting magnets use an advanced cable-in-conduit conductor (CICC) design similar to that developed in support of the International Thermonuclear Experimental Reactor (ITER). The toroidal field magnets provide 4.0 T at 2.25 m with a stored energy of 1.05 GJ. The poloidal field magnets provide 18.0 V-s to ohmically start and control long burns of a 2.0 MA plasma.

A comparison between niobium titanium and Nb3Sn cable-in-conduit conductors (CICC) was carried out at 8 K. The study was conducted to verify the required operating temperature, critical current density and energy margin of superconducting coils used in magnetically levitated transport systems for levitation and propulsion purposes. The results demonstrated the superiority of the Nb3Sn CICC over other conductors.

Investigates the efficacy of amitriptyline on the treatment of endogenous depression. Correlation between plasma concentration and therapeutic response with nortriptyline; Production of nortriptyline following demethylation of the amitriptyline; Relationship between plasma concentrations and clinical response of the patient.