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U.S. Department of Energy
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Beryllium/molten salt blanket: a new blanket concept

Conference ·
OSTI ID:6087557
The Beryllium/Molten Salt (Be/MS) blanket is an interesting contender for fissile breeding fusion reactors. Beryllium is used for neutron multiplication, and a Li and Th containing molten salt is used for on line removal of bred fusile (T) and fissile (U233) fuels. A conceptual Be/MS blanket is described and its neutronic performance is estimated. The Be/MS blanket has unique characteristics that may be advantageous and their potential advantages are presented.
Research Organization:
California Univ., Livermore (USA). Lawrence Livermore Lab.
DOE Contract Number:
W-7405-ENG-48
OSTI ID:
6087557
Report Number(s):
UCRL-82663; CONF-790117-3
Country of Publication:
United States
Language:
English