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/sup 233/U breeding and neutron multiplying blankets for fusion reactors

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:7241468
A variety of blankets for fusion reactors were neutronically analyzed to determine the fusion energy multiplication factor (M), the heavy metal fission rate, the fissile atom production rate, and tritium production. The blankets studied were: (1) thorium metal, ThO/sub 2/, ThC/sub 2/, uranium metal, UO/sub 2/, UC, and UC/sub 2/ fast-fissioning blankets, (2) nonfissioning thorium metal blankets, (3) blankets that multiply neutrons in a /sup 238/U region and use those neutrons to breed tritium and /sup 233/U in a separate zone, and (4) beryllium, niobium, and molybdenum neutron-multiplying /sup 233/U breeding blankets.
Research Organization:
Univ. of California, Livermore
OSTI ID:
7241468
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 30:1; ISSN NUTYB
Country of Publication:
United States
Language:
English