Nuclear Science and Engineering / Volume 9 / Number 3 / March 1961 / Pages 346-356
Technical Paper / dx.doi.org/10.13182/NSE61-A25886
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A compact forced-circulation test loop for obtaining corrosion data applicable to molten-salt-fueled reactors has been operated in the MTR (HB-3) beam hole. Several tests were conducted with two fused-salt mixtures, NaF-ZrF4-UF4 and Li7F-BeF2-UF4, in loops constructed, respectively, of Inconel and INOR-8 (nominal composition: 70% Ni, 16% Mo, 7% Cr, 5% Fe, 2% other alloying elements). The maximum loop temperature ranged from 1300 to 1600°F. Engineering aspects of loop design and operation are described.