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

Fission-suppressed blankets for fissile fuel breeding fusion reactors

Journal Article · · J. Fusion Energy; (United States)
DOI:https://doi.org/10.1007/BF01050362· OSTI ID:5136749
Two blanket concepts for deuterium-tritium (DT) fusion reactors are presented which maximize fissile fuel production while at the same time suppress fission reactions. By suppressing fission reactions, the reactor will be less hazardous, and thereforeeasier to design, develop, and license. A fusion breeder operating a given nuclear power level canproduce much more fissile fuel by suppressing fission reactions. The two blankets described use beryllium for neutron multiplication. One blanket uses two separate circulating molten salts: one salt for tritium breeding and the other salt for U-233 breeding. The other uses separate solid forms of lithium and thorium for breeding and helium for cooling.
Research Organization:
Lawrence Livermore National Lab., Univ. of California, Berkeley, CA
OSTI ID:
5136749
Journal Information:
J. Fusion Energy; (United States), Journal Name: J. Fusion Energy; (United States) Vol. 1:3; ISSN JFEND
Country of Publication:
United States
Language:
English

Similar Records

Tritium breeding in a fusion--fission hybrid breeder reactor
Technical Report · Tue May 23 00:00:00 EDT 1978 · OSTI ID:6531756

/sup 233/U breeding and neutron multiplying blankets for fusion reactors
Journal Article · Thu Jul 01 00:00:00 EDT 1976 · Nucl. Technol.; (United States) · OSTI ID:7241468

High performance, suppressed-fission ICF hybrid
Conference · Wed Nov 30 23:00:00 EST 1983 · OSTI ID:5193276