Tritium breeding blanket
- Argonne National Lab., IL (USA)
- Oak Ridge National Lab., TN (USA)
- Japan Atomic Energy Research Inst., Tokyo (Japan)
- California Univ., Los Angeles, CA (USA)
- Wisconsin Univ., Madison, WI (USA)
- ENEA, Frascati (Italy). Centro Ricerche Energia
The terms of reference for ITER provide for incorporation of a tritium breeding blanket with a breeding ratio as close to unity as practical. A breeding blanket is required to assure an adequate supply of tritium to meet the program objectives. Based on specified design criteria, a ceramic breeder concept with water coolant and an austenitic steel structure has been selected as the first option and lithium-lead blanket concept has been chosen as an alternate option. The first wall, blanket, and shield are integrated into a single unit with separate cooling systems. The design makes extensive use of beryllium to enhance the tritium breeding ratio. The design goals with a tritium breeding ratio of 0.8--0.9 have been achieved and the R D requirements to qualify the design have been identified. 4 refs., 8 figs., 2 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6215071
- Report Number(s):
- CONF-901007-59; ON: DE91007754; TRN: 91-004498
- Resource Relation:
- Conference: 9. topical meeting on technology of fusion energy, Oak Brook, IL (USA), 7-11 Oct 1990
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BREEDING BLANKETS
DESIGN
BERYLLIUM
FIRST WALL
ITER TOKAMAK
LITHIUM
SPECIFICATIONS
TEMPERATURE DISTRIBUTION
TRITIUM RECOVERY
ALKALI METALS
ALKALINE EARTH METALS
CLOSED PLASMA DEVICES
ELEMENTS
METALS
REACTOR COMPONENTS
RECOVERY
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES
700201* - Fusion Power Plant Technology- Blanket Engineering