DESIGN OF AN EDDY-CURRENT BRAKE FOR A SODIUM-COOLED NUCLEAR POWER REACTOR | Zendy

R. S. Baker | Zendy

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DESIGN OF AN EDDY-CURRENT BRAKE FOR A SODIUM-COOLED NUCLEAR POWER REACTOR

Author(s) -

R. S. Baker

Publication year - 1958

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/4168764

Subject(s) - piping , nuclear engineering , eddy current brake , brake , mechanics , thermocouple , throttle , materials science , eddy current , electrical engineering , mechanical engineering , engineering , physics , composite material , metallurgy

Two eddy-current electromagnets to act as brskes were designed and installed in the sodium-cooled nuclear pcwer reactor SRE to throttle sodium flow throughout the reactor after shutdown in order to maintain a constant reactor temperature gradient. One brake was used on the primary piping system, the other on the secondary system. It was determined that the eddy-current brake should cause a dragging pressure of 0.3 psi at a flow rate of 12 gal/min. The flux density necessary to produce this pressure was calculated, and the coil ampere- turns required to produce this fiux density were determined. Both brakes were controlled by thermocouples and performance was satisfactory. (M.C.G.

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