Abstract
This paper describes the development of measurement and control techniques for radioactive materials in liquid sodium systems, as applied to the Fast Flux Test Facility (FFTF). The FFTF is a three-loop, sodium cooled fast reactor located on the U.S. Department of Energy (USDOE) Hanford Site in Washington state. It achieved criticality in 1980, operated at its full rated power of 400 MWt until 1986, operated at 291 MWt from 1986 until 1992, and is now (March 1993) in standby condition. Three primary loops transfer heat from the core to intermediate heat exchangers (IHX), which in turn transfer the heat to the secondary sodium system. The secondary system consists of three independent loops, each connected to an air-dump heat exchanger. Sodium purification is achieved by one cold trap on the primary system and one cold trap on each of the secondary loops. The cold traps are normally on line, but have been taken off line on occasion for repairs. A trap to remove radioactive cesium from primary sodium has been operated since 1987.
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Brehm, W.F. (1995). Transport of Radioactive Material in Liquid Sodium. In: Borgstedt, H.U., Frees, G. (eds) Liquid Metal Systems. Springer, Boston, MA. https://doi.org/10.1007/978-1-4615-1977-5_1
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DOI: https://doi.org/10.1007/978-1-4615-1977-5_1
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