A new water-cooled lead blanket concept

Conference · Wed Mar 01 04:00:00 EST 1989 · Fusion Technol.; (United States)

OSTI ID:6277958

Cheng, E T; Creedon, R L; Wong, C P.C.; Sze, D K

Lead has been widely investigated as a candidate blanket material in the form of lithium-lead (Li17Pb83) eutectic for D-T fueled fusion reactors. A new lead blanket concept is conceived that could be cooled by pressurized water and which mitigates the potential plononium and chemical activity concerns. One of the new ideas in the new lead blanket concept is the minimization of the lithium content in the lithium-lead material in order to further reduce the chemical activity with water. The minimum lithium concentration in this new Li-Pb alloy for achieving a tritium breeding ratio of 1.2 is 5 at. %. The other new idea is to mitigate the polonium leakage concern by using sealed tubes containing the recommended Li-Pb material. The bred tritium will permeate through the tube walls into the water coolant and be extracted. The tritium inventory in the blanket will be primarily that in the water coolant, amounting to about 320 g.

• Research Organization: General Atomics, San Diego, CA (US); Argonne National Lab., Argonne, IL (US)
• OSTI ID: 6277958
• Report Number(s): CONF-881031-
• Conference Information: Journal Name: Fusion Technol.; (United States) Journal Volume: 15:2
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BREEDING BLANKETS
BREEDING RATIO
CHEMICAL REACTIONS
CONVERSION RATIO
DEUTERIUM
ELEMENTS
HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
IRRADIATION REACTORS
ISOTOPES
LEAD ALLOYS
LIGHT NUCLEI
LITHIUM ALLOYS
MATERIALS TESTING
METALS
NUCLEI
ODD-ODD NUCLEI
OXYGEN COMPOUNDS
POLONIUM
REACTOR COMPONENTS
REACTORS
STABLE ISOTOPES
TESTING
TRITIUM PRODUCTION REACTORS
WATER
WATER COOLED REACTORS