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! ANP QUARTERLY PROGRESS REPORT 11. RECOVERYANDREPROCESSINGOFREACTOR FUEL G. I. Cathers M. R. Bennett W. K. Eister A plant for recovering (in seven batches) the uranium from the ARE fuel and rinse by the fluoride- volatility process is being designed, and con- struction is scheduled for completion by December 31, 1955. It is estimated that the amount of material to be processed will be 12.4 ft3 of NaF-ZrF,- UF, containing 65 kg of uranium, This plant will demonstrate, on a pilot-plant scale, the feasibility of the fluoride-volatility process as applied to the processing of the fuel from a circulating-fuel aircraft reactor. The feasibility of this process (Fig. 11.1) has been established on a laboratory scale.’*2 The basic equipment as now envisioned will consist of a fluorinator, an absorption column packed with NaF, a cold-trap system, and a fluorine disposal dnit. The fluoride-volatil ity process can be adapted for recycling uranium to a fresh fuel concentrate by adding a UF, reduction step and dissolving I D. E. Ferguson et al., ANP Quar. Prog. Rep. Sept. IO, 1954, ORNL-1771, p 12. * 2G. 1. Cathers, Recovery and Decontamination of Uranium from Fused Fluoride Fuels by Fluorination, ORNL-1709 (May 26, 1954). I WASTE SALT > 999b F P
3 - Z . * c * i PERIOD ENDING DECEMBER 10,7954 TABLE 11.1. DECONTAMINATION OBTAINED IN THE FLUORIDE-VOLATILITY PROCESS BY SCRUBBING UF6 Synthetic ARE fuel, prepared by hydrofluorination of 6 g of irradiated uranium metal in 67 g of NaF-ZrF4 (56-44 mole X), fluorinated at 65OoC with 40- to 80-fold excess fluorine. Run 1: UF6 product plus excess fluorine passed through 67 g of molten NaF-ZrF4 at 65OoC into a dry-ice trap and then resublimed into second trap. Runs 2 and 3: UF, product separated from excess fluorine in dry-ice trap and then volatilized through a C8Fl, still into a second trap. Beta Decontami nati on Factors Activity Run 1 Run 2 Run 3 Over-al I Scrub* Over-a1 I Scrub* Over-al I Scrub* Gross 4800 2.7 290 Ru 350 2.3 16 Zr 3.2 lo4 6.8 x lo4 Nb 1800 47 1200 1.2 250 2.2 14 4.7 lo4 TRE 2 x 106 2 x 10, 2 105 *Decontamination factor calculated for scrub step alone on basis of activity extracted from scrub material. Scrubbing the UF, product from the fluorination and sublimation steps with fluorocarbon (C,Fl,) did not improve the decontamination (runs 2 and 3, Table 11.1). Approximately 9 g of UF, sublimed from a fluorination run, was passed into the bottom of a C,F, distillation column (0.5 in. in diameter by 14 in. high, packed with t2-in. nickel Fenske helices) that was operating at full reflux at about gas had to be refluorinated from the NaF bed at 65OOC before being trapped. However, the gross decon- 86 tamination factors in the two fractions were of the same order, that is, 2 x lo3. The uranium loss on the NaF was only 0.01%. Two experiments were then performed with 30-9 beds of 20- to 40-mesh NaF held at 65OOC to eliminate the refluorination step (runs 2 and 3, Table 11.2). The results in both tests showed high absorption of ruthenium and niobium beta activities, and the over-till gross 4 beta decontamination factor was greater than 10 . eral, 1 to 10% of Nearly all the niobium activity was accounted for in the reactor and fused salt, while 7555 of the
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