Shield design for next-generation, low-neutron-fluence, superconducting tokamaks
A shield design using stainless steel (SST), water, boron carbide, lead, and concrete materials was developed for the next-generation tokamak device with superconducting toroidal field (TF) coils and low neutron fluence. A device such as the Tokamak Fusion Core Experiment (TFCX) is representative of the tokamak design which could use this shield design. The unique feature of this reference design is that a majority of the bulk steel in the shield is in the form of spherical balls with two small, flat spots. The balls are purchased from ball-bearing manufacturers and are added as bulk shielding to the void areas of builtup, structural steel shells which form the torus cavity of the plasma chamber. This paper describes the design configuration of the shielding components.
- Research Organization:
- Fusion Engineering Design Center/McDonnell Douglas Astronautics Company, Oak Ridge National Laboratory, Oak Ridge, TN
- OSTI ID:
- 6010954
- Report Number(s):
- CONF-850310-
- Journal Information:
- Fusion Technol.; (United States), Vol. 8:1; Conference: 6. topical meeting on the technology of fusion energy, San Francisco, CA, USA, 3 Mar 1985
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
SHIELDS
DESIGN
NEUTRON FLUENCE
TOKAMAK TYPE REACTORS
SUPERCONDUCTING MAGNETS
BALL BEARINGS
BORON CARBIDES
CONCRETES
SHIELDING MATERIALS
SPHERES
STAINLESS STEELS
TFCX REACTORS
WATER
ALLOYS
BEARINGS
BORON COMPOUNDS
BUILDING MATERIALS
CARBIDES
CARBON COMPOUNDS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
HYDROGEN COMPOUNDS
IRON ALLOYS
IRON BASE ALLOYS
MAGNETS
MATERIALS
OXYGEN COMPOUNDS
STEELS
SUPERCONDUCTING DEVICES
THERMONUCLEAR REACTORS
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700209 - Fusion Power Plant Technology- Component Development & Materials Testing