ITER blanket and shield studies for high aspect ratio design option
- Argonne National Lab., IL (United States)
- Oak Ridge National Lab., TN (United States)
- California Univ., Los Angeles, CA (United States)
- Wisconsin U
The attractiveness of the high aspect ratio design (HARD) option for ITER has motivated a study to assess the blanket and shield design performance for this configuration relative to the ITER reference design. The blanket and shield have been configured to take an advantage of the HARD option. The layered solid breeder blanket concept with water-coolant and steel-structure and the water-steel shield have been used. The changes in the neutron wall loading distribution, the mechanical design, the net tritium breeding ratio, the total tritium inventory, and the nuclear heating profiles are evaluated. The tradeoff between the net tritium breeding ratio, and the fuel operating cost is analyzed. The mechanical design and the structural interaction between the first wall and the blanket is studied. 4 refs., 3 figs., 5 tabs.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6150156
- Report Number(s):
- ANL/CP-73462; CONF-910968-41; ON: DE92003376
- Resource Relation:
- Conference: 14. IEEE symposium on fusion engineering, San Diego, CA (United States), 30 Sep - 3 Oct 1991
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
Ma
BREEDING BLANKETS
DESIGN
ITER TOKAMAK
SHIELDING
ASPECT RATIO
NEUTRON FLUENCE
NEUTRON REACTIONS
RADIATION HEATING
WALL LOADING
BARYON REACTIONS
CLOSED PLASMA DEVICES
HADRON REACTIONS
HEATING
NUCLEAR REACTIONS
NUCLEON REACTIONS
POWER DENSITY
REACTOR COMPONENTS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700420* - Fusion Technology- Plasma-Facing Components- (1992-)
700480 - Fusion Technology- Component Development
Materials Studies- (1992-)