Lotus lithium-lead fusion blanket concept for neutronics experiments

Journal Article · Tue May 01 00:00:00 EDT 1990 · Fusion Technology; (United States)

OSTI ID:5306940

Azam, S ^[1]; Kumar, A ^[2]

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1. Inst. de Genie Atomique Ecole Polytechnique Federale de Lausanne CH-1015 Lausanne (CH)
2. Univ. of California at Los Angeles, Mechanical, Aerospace, and Nuclear Engineering Dept., Los Angeles, CA (US)

The objective of the LOTUS experimental program, is to perform various integral neutronics measurements like neutron spectrometry, activation, and tritium breeding ratio (TBR) on fusion reactor blanket concepts. The first blanket concept studied at the LOTUS facility was the fission-suppressed type. Investigations of pure fusion blanket concepts constitute a logical continuation of this program., The new LOTUS fusion blanket concept employs a eutectic of lithium and lead, for example, 17L-83Pb, and lithium-metal as tritium breeders. The blanket consists of a first wall of low-activation ferritic steel, followed by zones of 17Li-83Pb, {sup 6}Li, and a reflector made of graphite or silicon carbide (SiC). The choice of structural material for each zone is based on its compatibility with the primary zonal component. Vanadium alloy (V-15 Cr-5 Ti), low-activation ferritic steel (Fe-11 Cr-2.5 W-0.3 V-0.15 C), and the same vanadium alloy were retained for 17Li-83Pb, {sup 6}Li, and graphite or SiC zones, respectively. This paper reports on one-dimensional ANISN calculations carried out for the optimization of the blanket dimensions.

• OSTI ID: 5306940
• Journal Information: Fusion Technology; (United States), Vol. 17:3; ISSN 0748-1896
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
MATERIALS TESTING
ACTIVATION ANALYSIS
BREEDING RATIO
FERRITIC STEELS
LEAD
LITHIUM 6
LOTUS FACILITY
NEUTRONS
REACTOR KINETICS
SILICON CARBIDES
TEST FACILITIES
THERMONUCLEAR REACTORS
TRITIUM
VANADIUM ALLOYS
ALKALI METAL ISOTOPES
ALLOYS
BARYONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CARBIDES
CARBON COMPOUNDS
CHEMICAL ANALYSIS
CONVERSION RATIO
ELEMENTARY PARTICLES
ELEMENTS
FERMIONS
HADRONS
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
KINETICS
LIGHT NUCLEI
LITHIUM ISOTOPES
METALS
NUCLEI
NUCLEONS
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
SILICON COMPOUNDS
STABLE ISOTOPES
STEELS
TESTING
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering
700209 - Fusion Power Plant Technology- Component Development & Materials Testing