
doi: 10.2172/4659092
This report describes the design and fabrication of an electrically heated test section that was used to simulate the heat transport associated with the handling, after irradiation and discharge from the reactor vessel, of a fueled Fast Flux Test Facility (FFTF) closed loop test assembly while in the air-cooled ex-vessel handling machine.
Engineered Safeguards, Sodium, (E), Test Reactors--Auxiliary Systems &Amp, Mockup, Fftf Reactor, Heat Transfer, Fast Flux Test Facility/Fuel Assembly Handling In, 620, N78560* --Research &Amp, After-Heat Removal, Decay Heat Removal By Combined Loop Ex-Vessel Machine For Irradiated, Fuel Assemblies, Spent Fuel Storage Fast Flux Test Facility/Fuel Assembly Handling In
Engineered Safeguards, Sodium, (E), Test Reactors--Auxiliary Systems &Amp, Mockup, Fftf Reactor, Heat Transfer, Fast Flux Test Facility/Fuel Assembly Handling In, 620, N78560* --Research &Amp, After-Heat Removal, Decay Heat Removal By Combined Loop Ex-Vessel Machine For Irradiated, Fuel Assemblies, Spent Fuel Storage Fast Flux Test Facility/Fuel Assembly Handling In
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