Shielding aspects of D- sup 3 He fusion power reactors
- Wisconsin Univ., Madison, WI (United States). Fusion Technology Inst.
In this paper the implications of the D-{sup 3}He fuel cycle on shielding design are investigated for tokamak power reactors of the ARIES/Apollo class. The prime function of the shield is to protect the superconducting magnets against radiation. A variety of shield options is examined, and the various shields are optimized for the D-{sup 3}He neutron spectrum. The results demonstrate the relative merits of the various materials as a function of the shield thickness. In the first wall/shield, low-activation structural materials (such as Tenelon, modified HT-9, silicon carbide composites, and carbon-carbon composites) were employed to reduce the radioactive inventory and increase the safety margin in case of accidents. A comparison between the different shield options based on detailed neutronics, environmental/safety, and economic assessments has led to the selection of the reference shield design. The first-wall/shield structure is made of an elementally tailored ferritic steel (MHT-9), and the thermal energy is converted through an organic coolant at 44% efficiency. The safety features of the low-activation steel shield, along with the low neutron production in the D-{sup 3}He fuel cycle, enable the ARIES-III/Apollo design to achieve acceptable environmental and safety characteristics.
- OSTI ID:
- 7284758
- Journal Information:
- Fusion Technology; (United States), Vol. 22:1; ISSN 0748-1896
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
Ma
Fu
36 MATERIALS SCIENCE
ENVIRONMENT
SAFETY
HELIUM 3 TARGET
DEUTERON REACTIONS
SHIELDING
DESIGN
MATERIALS TESTING
FERRITIC STEELS
FIRST WALL
FUEL CYCLE
HELIUM COOLED REACTORS
NEUTRON SPECTRA
RADIATION EFFECTS
SUPERCONDUCTING MAGNETS
TOKAMAK TYPE REACTORS
ALLOYS
CHARGED-PARTICLE REACTIONS
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
GAS COOLED REACTORS
IRON ALLOYS
IRON BASE ALLOYS
MAGNETS
NUCLEAR REACTIONS
REACTORS
SPECTRA
STEELS
SUPERCONDUCTING DEVICES
TARGETS
TESTING
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
700480* - Fusion Technology- Component Development
Materials Studies- (1992-)
700460 - Fusion Technology- Heating & Fueling Systems
Fuels- (1992)
360106 - Metals & Alloys- Radiation Effects