Thermal hydraulics of handling FFTF fuel in sodium and argon, comparing test results with calculated

Tests were performed to assess the temperature distributions in FFTF fuel as they are handled in transfer pots, as bare assemblies and in partial fuel pin arrays. The detailed thermal mapping needed for handling FFTF fuel in storage locations, in and out of the reactor, and during transfers in handling machines has been obtained for fuel in stagnant sodium and stagnant atmospheres of argon and helium. Tests also include the thermal assessment of fuel under conditions of forced cooling with argon. The fuel cladding handling thermal limit for preserving reactor test information is 426.7/sup 0/C and in certain instances a local value of 537.9/sup 0/C is allowed for short periods of time. The cladding integrity thermal limit for FFTF fuel is 871.1/sup 0/C. Fuel with a maximum decay heat of 10 kW can be transferred in a sodium filled transfer pot which has been externally conditioned for a high surface emissivity to meet a data preservation thermal limit of 426.7/sup 0/C. The decay heat limit for handling fuel in stagnant argon is less than 1 kW, if data is to be preserved, and forced cooling of a 5 kW decay heat assembly with argon requires a flow of at least more » .023 CMS (49 SCFM). Results from the electrical tests of prototypic fuel assembly and pin arrays have identified thermal/hydraulic margins of conservatism and have allowed for the meaningful design handling equipment. Analytical thermal models show favorable agreement with the test results. 12 figures. « less