Shield design for next-generation, low-neutron-fluence, superconducting tokamaks

Conference · Tue Jan 01 04:00:00 EST 1985

OSTI ID:5544763

Lee, V D; Gohar, Y

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 built-up, structural steel shells which form the torus cavity of the plasma chamber. This paper describes the design configuration of the shielding components.

• Research Organization: Oak Ridge National Lab., TN (USA); Argonne National Lab., IL (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5544763
• Report Number(s): CONF-850310-92; ON: DE85011409
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BORON CARBIDES
BORON COMPOUNDS
BUILDING MATERIALS
CARBIDES
CARBON COMPOUNDS
CHROMIUM ALLOYS
CONCRETES
CORROSION RESISTANT ALLOYS
DESIGN
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
ELEMENTS
EQUIPMENT
HYDROGEN COMPOUNDS
IRON ALLOYS
IRON BASE ALLOYS
LEAD
MAGNETS
MATERIALS
METALS
OXYGEN COMPOUNDS
SHIELDING
STAINLESS STEELS
STEELS
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
TFCX REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
WATER