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

Conference ·
OSTI ID:6294972
; ; ;
Liquid lithium-lead eutectic alloy (17 at % Li-83 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 over-pressure 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:
Argonne National Lab., IL (USA); McDonnell Douglas Astronautics Co., St. Louis, MO (USA)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
6294972
Report Number(s):
CONF-830406-45; ON: DE83011695
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
ALLOY-HT-9
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
DESIGN
FIRST WALL
FLUID MECHANICS
HYDRAULICS
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LEAD ALLOYS
LIGHT NUCLEI
LITHIUM ALLOYS
MECHANICS
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
RECOVERY
SAFETY
STEELS
THERMONUCLEAR REACTOR WALLS
TRITIUM
TRITIUM RECOVERY
VANADIUM ALLOYS
YEARS LIVING RADIOISOTOPES