Aqueous self-cooled blankets for next-generation fusion devices
Thesis/Dissertation
·
OSTI ID:5924694
The Aqueous Self-Cooled Blanket (ASCB) concept is based on the use of water, with small amounts of lithium compounds, as both the coolant and the breeding medium. This work addresses all the major issues associated with the application of the ASCB to next-generation fusion devices, including the analysis of: (1) tritium breeding potential of ASCB-based blanket designs; (2) shielding performance of ASCB-based blankets and shields; (3) potential neutron streaming paths (divertor duct or gaps at the shield); (4) issues associated with the tritium recovery system, the tritium control and the tritium concentration in the water coolant; (5) activation of the machine components, including the structure, the coolant and the corrosion products; (6) issues associated with the water chemistry (radiolysis) and with corrosion of the structural materials; and (7) issues related to the safety of the public, the workers and the facility itself. The main features of the ASCB based blanket and shield system are the following: First, the inherent simplicity of the concept results in highly reliable, safe, low-technology, and economically attractive designs. Second, the ASCB approach results in designs with good shielding and breeding characteristics. Finally, the analysis indicates that there are no issues that might cause the concept to be outright unfeasible or unapplicable to next-generation devices. Three outstanding issues which need further evaluation are: (1) tritium recovery and control; (2) corrosion (stress corrosion cracking); and (3) radiolysis. Preliminary results from experiments in all three areas indicate that none of the three issues can not be resolved.
- Research Organization:
- Rensselaer Polytechnic Inst., Troy, NY (USA)
- OSTI ID:
- 5924694
- Country of Publication:
- United States
- Language:
- English
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Fri Oct 31 23:00:00 EST 1986
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·
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·
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ACTIVITY LEVELS
ALKALI METAL COMPOUNDS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
BREEDING RATIO
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CONTROL
CONVERSION RATIO
COOLANTS
COOLING
CORROSION
CORROSION PRODUCTS
DECOMPOSITION
DESIGN
HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
NUCLEI
ODD-EVEN NUCLEI
OXYGEN COMPOUNDS
PERFORMANCE
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIOISOTOPES
RADIOLYSIS
REACTOR COMPONENTS
RECOVERY
SHIELDING
TEST FACILITIES
THERMONUCLEAR DEVICES
TRITIUM
TRITIUM RECOVERY
WATER
WATER CHEMISTRY
YEARS LIVING RADIOISOTOPES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ACTIVITY LEVELS
ALKALI METAL COMPOUNDS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
BREEDING RATIO
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CONTROL
CONVERSION RATIO
COOLANTS
COOLING
CORROSION
CORROSION PRODUCTS
DECOMPOSITION
DESIGN
HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
NUCLEI
ODD-EVEN NUCLEI
OXYGEN COMPOUNDS
PERFORMANCE
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIOISOTOPES
RADIOLYSIS
REACTOR COMPONENTS
RECOVERY
SHIELDING
TEST FACILITIES
THERMONUCLEAR DEVICES
TRITIUM
TRITIUM RECOVERY
WATER
WATER CHEMISTRY
YEARS LIVING RADIOISOTOPES