Published November 1979 | Version v1
Report Restricted

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

Description

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/m2 with the first-wall temperature not exceeding 4500C 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

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.

Files

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Additional details

Publishing Information

Imprint Pagination
38 p.
Report number
WFPS-TME--79-031