Mechanical design and thermal hydraulic considerations for a self-cooled lithium-lead blanket
Conference
·
· Nucl. Technol./Fusion; (United States)
OSTI ID:6263767
Liquid lithium-lead eutectic alloy (17 at-% Li83 at-% Pb, referred to herein as Li-Pb) is currently being considered as a candidate breeding material for fusion reactors. Some important considerations in the design of a Li-Pb blanket are compatibility with the structure, tritium containment and recovery, and safety. Additional design complexities arise because of the high density of Li-Pb, the relatively high melting temperature (235/sup 0/C), and the high tritium overpressure associated with this alloy. In this study, the Li-Pb eutectic was considered both as the breeder and as the coolant. Thermal hydraulic and stress analyses were conducted to assess the technical feasibility of using Li-Pb as the breeder and coolant based on DEMO reactor conditions. The results of the thermo-mechanical analyses showed that the elongated cylindrical blanket modules made from either HT-9 or vanadium alloy offer a viable first wall/blanket design concept.
- Research Organization:
- Fusion Power Program, Argonne National Lab., Argonne, IL 60439
- OSTI ID:
- 6263767
- Report Number(s):
- CONF-830406-
- Conference Information:
- Journal Name: Nucl. Technol./Fusion; (United States) Journal Volume: 4:2
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOY-HT-9
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
COOLANTS
DENSITY
ENERGY TRANSFER
EUTECTICS
FEASIBILITY STUDIES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LEAD ALLOYS
LEAD BASE ALLOYS
LIGHT NUCLEI
LITHIUM ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICS
MELTING POINTS
NUCLEI
ODD-EVEN NUCLEI
PHYSICAL PROPERTIES
RADIOISOTOPES
REACTOR COMPONENTS
STEELS
STRESS ANALYSIS
TESTING
THERMAL ANALYSIS
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR MATERIALS
TRANSITION TEMPERATURE
TRITIUM
VANADIUM ALLOYS
VAPOR PRESSURE
YEARS LIVING RADIOISOTOPES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOY-HT-9
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
COOLANTS
DENSITY
ENERGY TRANSFER
EUTECTICS
FEASIBILITY STUDIES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LEAD ALLOYS
LEAD BASE ALLOYS
LIGHT NUCLEI
LITHIUM ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICS
MELTING POINTS
NUCLEI
ODD-EVEN NUCLEI
PHYSICAL PROPERTIES
RADIOISOTOPES
REACTOR COMPONENTS
STEELS
STRESS ANALYSIS
TESTING
THERMAL ANALYSIS
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR MATERIALS
TRANSITION TEMPERATURE
TRITIUM
VANADIUM ALLOYS
VAPOR PRESSURE
YEARS LIVING RADIOISOTOPES