High performance, suppressed-fission ICF hybrid

Conference · Wed Nov 30 23:00:00 EST 1983

OSTI ID:5193276

Meier, W R

The neutronics aspects of an ICF hybrid concept are discussed. The breeding blanket consists of a beryllium neutron multiplier, metallic thorium fertile fuel and a liquid-lithium coolant. The fertile fuel fraction is 30 vol%, which is much higher than previous one-zone, suppressed-fission hybrid concepts. Fission in the bred /sup 233/U is suppressed by competition from tritium breeding reactions in /sup 6/Li. The total breeding ratio, T + F, is 2.05, and the total neutron energy deposited is 41.1 MeV per DT neutron. The 800-MW (fusion) hybrid produces approx. 3500 kg of /sup 233/U per full-power-year.

• Research Organization: Lawrence Livermore National Lab., CA (USA)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 5193276
• Report Number(s): UCRL-89274; CONF-831203-116; ON: DE84008298
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700208 -- Fusion Power Plant Technology-- Inertial Confinement Technology
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALKALINE EARTH METALS
ALPHA DECAY RADIOISOTOPES
BERYLLIUM
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING RATIO
CONFINEMENT
CONVERSION RATIO
ELEMENTS
EVEN-ODD NUCLEI
HEAVY NUCLEI
HYBRID REACTORS
HYDROGEN ISOTOPES
INERTIAL CONFINEMENT
ISOTOPES
LIGHT NUCLEI
METALS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
PLASMA CONFINEMENT
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR COMPONENTS
TRITIUM
URANIUM 233
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES