In some cases, tentative designs were selected. Alternative design concepts were identified, developed, and evaluated. Scoping studies were performed of the major components and subsystems of the 3.8 m ITR. Both designs employ 12 superconducting NbTi toroidal field coils built up in pancake windings with stainless steel interleaving the conductor windings. Water-cooled steel with lead cover layers is used for the bottom shield, while the other outboard shields are built up of stainless steel, boronated water, and lead. Water-cooled tungsten blocks, stacked in annular stainless steel tanks together with the inboard field-shaping coils, are used as the inboard shield. The exposed walls of the chamber are coated with a carbon deposit. Both reactors utilize a water-cooled Inconel 625 plasma chamber more » with graphite tiles lining the inboard walls and movable limiters at the top and bottom of the chambers. The 4.2 m UITR is designed to be operated initially as an ITR and later be upgraded for net power Experimental Power Reactor (EPR) operation at a duty factor of 0.78. The 3.8 m ITR is designed to achieve D-T ignition and maintain 30-second burns at a low duty factor of 0.1. Both reactors are based on a doublet plasma cross section which enables them to achieve high. = ,Ĭonceptual designs have been developed for a 3.8 m Ignition Test Reactor (ITR) and a 4.2 m Upgradable Ignition Test Reactor (UITR).
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