Mechanical design and thermal hydraulic considerations for a self-cooled lithium-lead blanket

Conference · Thu Sep 01 00:00:00 EDT 1983 · Nucl. Technol./Fusion; (United States)

OSTI ID:6263767

Misra, B; Smith, D L

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-; TRN: 85-002351
• Journal Information: Nucl. Technol./Fusion; (United States), Vol. 4:2; Conference: 5. topical meeting on technology of fusion energy, Knoxville, TN, USA, 26 Apr 1983
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
THERMONUCLEAR REACTOR MATERIALS
LEAD BASE ALLOYS
HEAT TRANSFER
HYDRAULICS
STRESS ANALYSIS
LITHIUM ALLOYS
ALLOY-HT-9
COOLANTS
DENSITY
EUTECTICS
FEASIBILITY STUDIES
MATERIALS TESTING
MELTING POINTS
THERMAL ANALYSIS
TRITIUM
VANADIUM ALLOYS
VAPOR PRESSURE
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
ENERGY TRANSFER
FLUID MECHANICS
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LEAD ALLOYS
LIGHT NUCLEI
MATERIALS
MECHANICS
NUCLEI
ODD-EVEN NUCLEI
PHYSICAL PROPERTIES
RADIOISOTOPES
REACTOR COMPONENTS
STEELS
TESTING
THERMODYNAMIC PROPERTIES
TRANSITION TEMPERATURE
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering
700209 - Fusion Power Plant Technology- Component Development & Materials Testing