Chemical equilibrium studies of tritium--lithium and tritium--lithium alloy systems
Description
In deuterium-tritium fusion reactors currently under design, the production of tritium is accomplished by utilizing a lithium-bearing blanket. Lithium metal is presently the leading candidate for the blanket material, although molten Li2BeF4, solid Li--Al (50-50 at. percent) alloy and other lithium-containing materials are distinct possibilities. This paper summarizes progress of ongoing studies of the thermodynamics of some of these lithium containing systems. The individual solubilities of hydrogen, deuterium, and tritium in lithium as a function of temperature (700 to 10000C) and pressure are presented. Recent work with the solid alloy Li--Al (50-50 at. percent) has shown that the tritium solubility between 400 and 6000C is low. When the tritium pressure was between 0.14 and 0.52 torr, the Li--Al samples contained only 1 to 4 ppm tritium
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Publishing Information
- Imprint Pagination
- 16 p.
- Report number
- CONF-751026--14
Conference
- Title
- International conference on radiation effects and tritium technology for fusion reactors.
- Dates
- 1 Oct 1975.
- Place
- Gatlinburg, Tennessee, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7234938
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM ALLOYS; BREEDING BLANKETS; DEUTERIUM; FLIBE; HYDROGEN; LITHIUM; LITHIUM ALLOYS; PERMEABILITY; SOLUBILITY; THERMONUCLEAR REACTORS; TRITIUM
- Descriptors DEC
- ALKALI METALS; ALLOYS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; ELEMENTS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; METALS; MOLTEN SALTS; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; RADIOISOTOPES; REACTOR COMPONENTS; SALTS; STABLE ISOTOPES; YEARS LIVING RADIOISOTOPES