Gas bubble nucleation and tritium permeation through metallic walls in a liquid 83Pb-17Li blanket
Journal Article
·
· Fusion Technol.; (United States)
OSTI ID:5806208
Recent studies have given lower and lower values for the solubility of hydrogen isotopes in the eutectic 83Pb-17Li alloy, a candidate breeding material for the blanket of fusion machines. Therefore, thermodynamic stability for the gaseous phase under the high pressure reached at the bottom of the alloy containers can be achieved even for very low tritium concentrations in the liquid phase. A mathematical model to determine when tritium bubble nucleation occurs at an appreciable rate is presented. This model is used to predict tritium production behavior in the next European Torus (NET) tokamak.
- Research Organization:
- Univ. di Cagliari, Dipt. di Ingegneria Chimica e Materiali, Piazza d'Armi 09100 Cagliari (IT); Joint Research Centre of the European Community Ispra Establishment, 21020 Ispra, Varese (IT)
- OSTI ID:
- 5806208
- Journal Information:
- Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 15:1; ISSN FUSTE
- Country of Publication:
- United States
- Language:
- English
Similar Records
A molten salt cooling 17Li-83Pb breeding blanket concept
Mathematical model applied to permeation problems of process designs for tritium recovery from liquid blankets
Self-cooled liquid-metal blanket concept
Conference
·
Mon Jul 01 00:00:00 EDT 1985
· Fusion Technol.; (United States)
·
OSTI ID:5794010
Mathematical model applied to permeation problems of process designs for tritium recovery from liquid blankets
Journal Article
·
Mon Sep 01 00:00:00 EDT 1986
· Fusion Technol.; (United States)
·
OSTI ID:5067428
Self-cooled liquid-metal blanket concept
Journal Article
·
Mon Oct 31 23:00:00 EST 1988
· Fusion Technol.; (United States)
·
OSTI ID:6244604
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METALS
BREEDING BLANKETS
BUBBLES
DATA
DESIGN
DIFFUSION
ELEMENTS
EXPERIMENTAL DATA
HYDROGEN ISOTOPES
INFORMATION
IRRADIATION REACTORS
ISOTOPES
LEAD
LITHIUM
MATERIALS TESTING
MATHEMATICAL MODELS
METALS
NET TOKAMAK
NUCLEATION
NUMERICAL DATA
PARAMETRIC ANALYSIS
REACTOR COMPONENTS
REACTORS
SOLUBILITY
TESTING
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM PRODUCTION REACTORS
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METALS
BREEDING BLANKETS
BUBBLES
DATA
DESIGN
DIFFUSION
ELEMENTS
EXPERIMENTAL DATA
HYDROGEN ISOTOPES
INFORMATION
IRRADIATION REACTORS
ISOTOPES
LEAD
LITHIUM
MATERIALS TESTING
MATHEMATICAL MODELS
METALS
NET TOKAMAK
NUCLEATION
NUMERICAL DATA
PARAMETRIC ANALYSIS
REACTOR COMPONENTS
REACTORS
SOLUBILITY
TESTING
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM PRODUCTION REACTORS