Lithium mass transport in ceramic breeder materials

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6156942

Blackburn, P E; Johnson, C E

The objective of this activity is to measure the lithium vaporization from lithium oxide breeder material under differing temperature and moisture partial pressure conditions. Lithium ceramics are being investigated for use as tritium breeding materials. The lithium is readily converted to tritium after reacting with a neutron. With the addition of 1000 ppM H{sub 2} to the He purge gas, the bred tritium is readily recovered from the blanket as HT and HTO above 400{degree}C. Within the solid, tritium may also be found as LiOT which may transport lithium to cooler parts of the blanket. The pressure of LiOT(g), HTO(g), or T{sub 2}O(g) above Li{sub 2}O(s) is the same as that for reactions involving hydrogen. In our experiments we were limited to the use of hydrogen. The purpose of this work is to investigate the transport of LiOH(g) from the blanket material. 8 refs., 1 fig., 3 tabs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6156942
• Report Number(s): CONF-901007-40; ON: DE91006449; TRN: 91-003205
• Resource Relation: Conference: 9. topical meeting on technology of fusion energy, Oak Brook, IL (USA), 7-11 Oct 1990
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
MASS TRANSFER
LITHIUM
EVAPORATION
DIFFUSION
LITHIUM HYDROXIDES
LITHIUM OXIDES
STAINLESS STEELS
TRITIUM
ALKALI METAL COMPOUNDS
ALKALI METALS
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHALCOGENIDES
ELEMENTS
HIGH ALLOY STEELS
HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
HYDROXIDES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
METALS
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
RADIOISOTOPES
REACTOR COMPONENTS
STEELS
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering
700209 - Fusion Power Plant Technology- Component Development & Materials Testing