Mechanical design and thermal hydraulic considerations for self-cooled lithium-lead blanket
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-31-109-ENG-38
- OSTI ID:
- 6294972
- Report Number(s):
- CONF-830406-45; ON: DE83011695
- Resource Relation:
- Conference: 5. topical meeting on technology of fusion energy, Knoxville, TN, USA, 26 Apr 1983; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BREEDING BLANKETS
DESIGN
HYDRAULICS
ALLOY-HT-9
BREEDING
FIRST WALL
LEAD ALLOYS
LITHIUM ALLOYS
SAFETY
TRITIUM
TRITIUM RECOVERY
VANADIUM ALLOYS
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
FLUID MECHANICS
HYDROGEN ISOTOPES
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
MECHANICS
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
RECOVERY
STEELS
THERMONUCLEAR REACTOR WALLS
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering