Plasma/Neutral Gas Transport in Divertors and Limiters 

Thesis (Sc.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1983.MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCEIncludes bibliographical references.by Paul Joseph Gierszewski.Sc.D

Helium-3 blankets for tritium breeding in fusion reactors

It is concluded that He-3 blankets offers considerable promise for tritium breeding in fusion reactors: good breeding potential, low operational risk, and attractive safety features. The availability of He-3 resources is the key issue for this concept. There is sufficient He-3 from decay of military stockpiles to meet the International Thermonuclear Experimental Reactor needs. Extraterrestrial sources of He-3 would be required for a fusion power economy

Plasma/neutral gas transport in divertors and limiters

Thesis (Sc.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1983.MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCEIncludes bibliographical references.by Paul Joseph Gierszewski.Sc.D