Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Potential for fissile breeding with the fusion-fission hybrid reactor

Conference ·
OSTI ID:7178052

The general features of the mirror reactor design are discussed. Details of the blanket-coil geometry are shown. The inside face of the blanket segments are divided into individual pressure vessels. These submodules contain fissile breeding material located directly behind the first wall, a fusile breeding material behind the fertile breeder, and then coolant inlet and outlet plena. Two blankets are examined and compared in this study. One contains natural uranium plus 7 wt. percent Mo, the second contains thorium metal. The performance of these blankets is discussed. (MOW)

Research Organization:
California Univ., Livermore (USA). Lawrence Livermore Lab.
DOE Contract Number:
W-7405-ENG-48
OSTI ID:
7178052
Report Number(s):
UCRL-77887; CONF-760622-30
Country of Publication:
United States
Language:
English