PROCESS AND APPARATUS FOR SEPARATING ACTINIDE OR LANTHANIDE METALS OR THEIR ALLOYS FROM SALTS

Abstract: A process and apparatus for separating molten uranium (13) from molten salts (6) in which molten salt (6) floats on a portion of the exposed surface of a molten uranium trap (8) or a molten alloy trap, leaving a portion of exposed surface free to discharge uranium or alloy (13) while retaining molten salt (6). In this way clean, massive alloy (14) can be recovered from scrap material which would otherwise be discarded.

Description: "PROCESS AND APPARATUS FOR SEPARATING ACTINIDE OR LANTHANIDE METALS OR THEIR ALLOYS FROM SALTS" DESCRIPTION This invention relates to processes and apparatus for the separation of actinide and lanthanide metals or alloys from salts, and more particularly for the separation of uranium or its alloys from molten halides or their mixtures. Nonexplosive penetrators for use against military armour are machined from depleted-uraniumalloy rods. Depleted uranium is formed from by-product uranium compounds depleted in the uranium-235 isotope because that isotope has been removed for use in nuclear reactors. Such isotope separation does not substantially alter the uranium chemistry or the properties of depleted-uranium-alloy rods. Potentially val uable uranium alloy in partially oxidised turnings from such machining, or in some other oxidised forms of uranium alloys, is normally discarded rather than recycled because small pieces of oxidised uranium alloys often do not melt to form massive uranium--the partial oxidation of the alloys produces a coating of uranium oxide which prevents the agglomeration of molten-alloy droplets. Melting of uranium requires a substantially inert environment, usually an inert-gas atmosphere. I have now found that marked technical improvement and corollary economies in the separations can be effected through the use of a molten-salt bath floating on a molten-alloy trap which together (a) wash the oxide coating away from the molten alloy, thereby allowing alloy agglomeration, and (b) permit substantially continuous separation of massive uranium alloy through the molten-alloy trap, such massive alloy being substantially free of oxides and salt from the molten-salt bath. The conversion of uranium oxide to uranium fluoride by reaction with hydrogen fluoride is known. I have now found that conversion of uranium oxide coatings to uranium fluorides is useful prior to separation through use of a molten-salt bath floating on a moltenalloy trap, as discussed in the previous paragraph-economies in such separations result because such uranium fluoride dissolves in said molten-salt bath and is more easily removed than is uranium oxide, which is substantially insoluble in said bath. Depleted uranium for alloy formation, e.g., for said penetrators, is usually produced by reaction of uranium fluoride with magnesium in high-pressure vessels at temperatures of about 13000C, thus melting uranium, at 11330, and magnesium fluoride, at 12610. If both materials have been molten throughout, the cold uranium product will be found in massive form and can readily be broken away from the magnesium fluoride byproduct. If, however, the pressure and temperature do not both rise to the high values required during reduction, part or all of the uranium will be trapped in solid magnesium fluoride as dispersed, frozen droplets rather than as massive, recoverable uranium. Under current practice uranium in such dispersed droplets is discarded; such lack of separation results in loss cf as much as five percent of the otherwise possible uranium production in commercial operations. I have now found that magnesium-fluoride-free massive uranium can be recovered from such dispersed droplets by melting them in a molten-salt bath floating on a moltenuranium trap; furthermore, such recovery can be substantially continuous. There is major economic advantage to recovery of such uranium. As was indicated above, the bath reductions of uranium fluoride by magnesium in pressure vessels do not always lead to useful products. I have now found that substantially continuous reduction of uranium fluoride by magnesium can be carried out by introducing said uranium fluoride and said magnesium into a moltensalt bath floating on a molten-uranium trap and allowing said reduction to take place within the molten-salt bath. It is further advantageous to operate said molten-salt bath in a temperature gradient such that the uranium trap and the adjacent molten salt are at about 11500C, i.e., above the uranium melting point, while the molten salt near the top of the bath is at about 10500C, i.e., below the boiling point of magnesium. The following examples illustrate but do not limit the invention:- Example 1 Oily, heavily oxidised coatings are present on the turnings produced during the machining of uranium alloy rods to form armour penetrators. Although the oil used is water soluble and can readily be washed off, the turnings are oxide coated and cannot alone be melted to massive alloys. Washed and dried oxidised turnings were melted, agglomerated, and recovered using a first molten-salt bath and a first molten-alloy trap in an apparatus described with reference to FIG. 1, as follows: In an inert atmosphere, molten-uranium alloy at 11500C was held in a first alumina cup 1 of 2-inch diameter, 4-inch high, filling it to a first moltenalloy pouring lip 2. This first molten-alloy pouring lip was positioned to pour into an alumina billet mold 3 below. There was provided a first alumina tube 4 of l-inch diameter, 20-inch high, open at both ends, with first molten-salt pouring tube 5 attached 19 inches up from the bottom of said first alumina tube. The bottom of this first alumina tube 4 was inserted three inches through the center of the exposed surface of the molten alloy in the cup, thereby creating a container with alumina tube sides and dense but movable molten-alloy bottom, which bottom could pass alloy but retain salt. Molten salt was formed when a mixture of 50 mole percent each of magnesium fluoride and calcium chloride was added into the alumina tube 4 and this halide mixture melted with liquidus temperature of approximately 975 0C. A temperature of 11500 was maintained throughout this bath. Addition of this molten salt caused displacement of a weight of uranium alloy equal to the weight of the molten salt added. The volume of molten alloy displaced from the first alumina cup was approximately one eighth the volume of the molten salt added, reflecting densities for uranium alloy of approximately 18 g/cm3 and for molten salt of approximately 2.25 g/cm3; (18/2.25) = 8. The volume of the molten salt 6 within the alumina tube was increased until the operating conditions were reached, namely until an approximately 18-inch column of molten salt 6 floated at an interface 7 between molten salt and molten alloy 8 within the alumina tube and approximately 2.25 inches lower than the surface of the molten alloy inside the first alumina cup 1 but outside the first alumina tube 4. This column of molten salt is the first moltensalt bath. If excess molten salt is added, the excess can be discharged through the first molten-salt pouring tube 5, discharging as drops 9 which fall into molten-salt discharge cup 10 and form collected discharge 11; this method of discharge establishes an upper limit to the height of the first molten-salt bath. Likewise, the molten alloy in the first alumina cup, as here configured, is the first molten-alloy trap. If uranium alloy is added 12, it can be separated as molten-alloy drops 13 after passing through the first molten-alloy trap, which drops collect as massive uranium alloy 14 in billet mold 3. Oxidised uranium alloy added to this first moltensalt bath and thence to the first molten-alloy trap led to separation of drops of clean molten alloy out of said molten-alloy trap, which drops formed a billet. There was no evidence of leakage of molten salt past the first molten-alloy trap. Except for pauses to change billet molds or for uranium oxide removal, this system could be operated continuously, producing reusable alloy from material which is not now recycled. Ceramic fragments (e.g., alumina of density 4 g/cm3) could be floated at the interface 7 to hold unmelted added uranium alloy until it dripped as a discontinuous phase through a contiunuous phase of molten salt. Such dripping assures substantially complete washing away of oxide from the uranium. Example 2 Oxidised machining turnings, as in Example 1, were washed and treated with 53% hydrofluoric acid for three minutes, thereby converting uranium oxide to uranium fluoride. Precipitation of a uranium-fluoride film on the uranium alloy substantially prevents reaction of hydrofluoric acid with uranium alloy during short exposures. The turnings were dried. In an apparatus as described for Example 1, this treated product, i.e., uranium alloy and uranium fluoride, was introduced into a molten-salt bath of composition 50 mole percent each of magnesium fluoride and calcium chloride at a temperature of 11509C Uranium fluoride from this treated product dissolved into this molten-salt bath, and uranium alloy melted and settled from this molten-salt bath. Clean uranium alloy separated through a molten-alloy trap. Uranium fluoride dissolved into the molten-salt bath, adding to the molten salt volume and causing discharge through a molten-salt pouring tube. If necessary, magnesium fluoride and calcium chloride can be added along with uranium alloy additions to maintain a suitable bath composition as uranium fluoride is added. This operation can be continuous throughout because massive uranium alloy is removed separately through the molten-alloy trap, and the uranium fluoride is removed through the molten-salt bath. Example 3 Crushed reject material from an inadequately melted commercial batch reduction of uranium fluoride was fed into a third molten-salt bath as in Example 1 and held at a temperature of 11506 throughout. Because the reject material contained approximately 30 mole percent of uranium and 62 mole percent of magnesium fluoride, along with impurities, the addition of this material would quickly alter the molten-alloy composition in this third molten-salt bath. Therefore, it was necessary to add calcium chloride equal in amount to the magnesium fluoride added with the reject material. Clean, massive uranium (not alloy this time) was separated continuously through the third molten-uranium trap, and by-product magnesium fluoride (plus calcium chloride) passed out through the third molten-salt pouring tube. Example 4 Uranium tetrafluoride, magnesium, and calcium chloride, in mole proportions 1:2.1:2, were fed as mixed pellets into a fourth molten-salt bath floating on a fourth molten-uranium trap, again as in Example 1. In this case the fourth molten-alloy bath was maintained in a temperature gradient, i.e., 10500 at the top and 11500 at the region of the fourth molten-uranium trap. Upon heating in the fourth molten-salt bath, the pellet materials reacted to form uranium and magnesium fluoride-calcium chloride molten salt. Clean, molten uranium was separated continuously through the fourth molten trap, and excess molten salt passed out through the fourth molten-salt pouring tube. It is believed thzt other actinide and lanthanide metals, such as plutonium and their alloys can be separated from salts by a process and apparatus in .-hicll this invention is embodied.

Claims: CLAIMS 1. A process for the separation for recovery of actinide or lanthanide metals or alloys in massive form which comprises liquifying a mixture of the metal or alloy within a molten salt bath (6) floating on a trap of the metal or alloy in a molten form. 2. A process for the separation for recovery of uranium in massive form which comprises liquifying a mixture of uranium or uranium alloy (12) within a molten salt'bath (6) floating on a molten uranium alloy trap (8) or a molten uranium trap. 3. A process according to Claim 2 in which oxidised uranium alloy or uranium (13) is separated for recovery. 4. A process according to Claim 3 in which uranium oxide is converted to uranium fluoride prior to separation. 5. A process according to any of Claims 2 to 4 in which uranium fluoride is reduced by magnesium prior to said separations. 6. A process according to any of Claims 2 to 5 in which uranium alloy or uranium to be separated is formed by reaction of uranium fluoride with magnesium. 7. A process according to any of Claims 2 to 6 in which the reactions are caused to take place while excluding gases which react with the metals or the salts. 8. Uranium or uranium alloy (14) whenever obtained by a process according to any of Claims 2 to 7. 9. An apparatus for separating molten actinide or lanthanide metal or metal alloy in massive form which comprises a molten salt bath (6) floating on a portion of the surface of a molten actinide or lanthanide metal trap or a molten actinide or lanthanide metal alloy trap, which trap retains molten salt but permits passage of molten actinide or lanthanide metal or alloy. 10. An apparatus for separating molten uranium or molten uranium alloy in massive form. which comprises a molten salt bath (6) floating on a portion of the surface of a molten uranium trap (8) or a molten alloy trap, which trap (8) retains molten salt but permits passage of molten uranium or molten uranium alloy (13).

Inventors: ELLIOTT, GUY RUPERT BETTS
Applicants: ELLIOTT, GUY RUPERT BETTS
Application year: 1985
Main classification: C22B60
IPC codes: C22B9, C22B60