Design of a stainless-steel helium-cooled first-wall for a tokamak reactor blanket

Technical Report · Thu Nov 01 04:00:00 EST 1979

OSTI ID:5873843

McDaniel, D T

This report summarizes the results of the thermal and hydraulic analysis on a magnetic fusion power reactor first-wall design that will be tolerant to minor coolant leaks. The design uses stainless steel as a structural material, liquid lithium as a heat conduction and tritium breeding material, and high pressure helium as a coolant. Bubbles of helium from minor leaks float to the surface of the liquid lithium where the gas is pumped off by a vacuum pump. The wall design is capable of absorbing heat flux densities up to 1.0 MW/m/sup 2/ with the first-wall temperature not exceeding 450/sup 0/C and the helium pumping power not exceeding 5% of the first wall thermal output. The performance characteristic curves which are developed provide a good basis for comparing first-wall designs.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA). Fusion Power Systems Dept.
• DOE Contract Number: AC02-77ET51010
• OSTI ID: 5873843
• Report Number(s): WFPS-TME-79-031; ON: DE82002469
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ALKALI METALS
ALLOYS
CHROMIUM ALLOYS
COOLANTS
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
DESIGN
ELEMENTS
ENERGY SYSTEMS
FIRST WALL
FLUID MECHANICS
FLUIDS
GASES
HELIUM
HIGH TEMPERATURE
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
LITHIUM
MECHANICS
METALS
NONMETALS
PHYSICAL PROPERTIES
RARE GASES
STAINLESS STEELS
STEELS
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS