A preliminary study was made of the vacuum system requirements for a D-T burning TEPR with major radius R = 6.25 m and plasma radius a = 2.1 m. Approximate requirements for the neutral injector vacuum system have been determined as functions of neutral beam power for a one-component, 180 keV D$sup 0$ beam derived from D$sup +$. For the 40 MW reference design D$sup 0$ beam, the total injector gas load varies from approximately 500 to approximately 800 Torr-l/ s as the assumed ion source gas efficiency varies from 40 to 25 percent. The torus or plasma containment vessel ...
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A preliminary study was made of the vacuum system requirements for a D-T burning TEPR with major radius R = 6.25 m and plasma radius a = 2.1 m. Approximate requirements for the neutral injector vacuum system have been determined as functions of neutral beam power for a one-component, 180 keV D$sup 0$ beam derived from D$sup +$. For the 40 MW reference design D$sup 0$ beam, the total injector gas load varies from approximately 500 to approximately 800 Torr-l/ s as the assumed ion source gas efficiency varies from 40 to 25 percent. The torus or plasma containment vessel has 711 m$sup 3$ of volume and 592 m$sup 2$ of surface area. Material selection for the first wall will affect the total gas load available to be pumped. The toroidal pumping system must be able to reduce the pressure after the burn or fusion cycle from 10$sup -3$ Torr to 10$sup -5$ Torr or less in 10 to 15 s. Furthermore, before each experimental run, or possibly more often, this pumping system must be capable of evacuating the entire volume down to 1 x 10$sup -8$ Torr or less to assure a reasonably contamination free plasma. (auth)
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Moenich, J.S.; Fasolo, J.A. & Stevens, H.C.Vacuum for a tokamak experimental fusion power reactor,
article,
January 1, 1975;
Illinois.
(digital.library.unt.edu/ark:/67531/metadc869518/:
accessed December 19, 2018),
University of North Texas Libraries, Digital Library, digital.library.unt.edu;
crediting UNT Libraries Government Documents Department.
