Patent Number: 040595390
Section: description

SUMMARY OF THE INVENTION The objects of this invention are obtained by nitriding a mixture of uranium and a minor amount not exceeding 10 percent by weight zirconium to produce a (U,Zr)N alloy product having enhanced thermal stability. The resultant nitrided product consists of a solution of zirconium mononitride within a solvent matrix of uranium mononitride. This product appears to be no different from pure UN and metallographic studies of the (U,Zr)N product show it to be a single-phase material. The X-ray diffraction pattern of a (U,Zr)N product is that of a body-centered cubic structure with an X-ray lattice parameter of 4.86 for a (U,Zr)N product containing 3.4 percent Zr by weight as opposed to 4.89 for pure UN. In addition to enhancing the high-temperature stability of UN at temperatures in excess of 1500.degree. C., the presence of ZrN appears to function as a stabilizing factor during the fabrication of a (U,Zr)N sintered compact to prevent formation of higher nitrides of uranium. The amount of Zr which is effective to stabilize the UN in these respects may vary from as little as 2 to as much as 10 weight percent, 3-5 being preferred. Lower amounts of Zr do not produce sufficient amounts of ZrN to impart a stabilizing effect to the resultant (U,Zr)N product. Greater amounts of Zr dilute the uranium excessively for nuclear fuel applications. The improved (U,Zr)N fuel of this invention may be conveniently prepared from a U-Zr alloy to convert the alloy to a (U,Zr)N product in accordance with the hydride-dehydride-nitride process as disclosed in U.S. Pat. No. 3,758,669. Beginning with a U-Zr alloy of the desired composition, the alloy is hydrided by a series of hydride-dehydride reactions to fragment and convert the alloy into a fine hydride powder. The hydrided alloy is then subjected to a series of dehydride-nitride cycles in which the alloy is heated to dehydride a portion of the alloy hydride and then cooled in a nitrogen atmosphere at a temperature lower than the dehydriding temperature to nitride the dehydrided portion. Succeeding dehydride-nitride cycles are conducted at dehydriding temperatures higher than the dehydriding temperature of the previous cycle until the entire charge has been converted to a (U,Zr)N powder, appearing virtually indistinguishable from pure UN. The (U,Zr)N is transferred to an inert atmosphere glove box and thence fabricated by binderless isostatic pressing at 6 .times. 10.sup.4 psi into rods. The rods are then transferred to a furnace and exposed to a sintering schedule involving treatment at 1500.degree. C. and then at a temperature in the range 2200.degree. to 2300.degree. C. in nitrogen at 760 torr for a period of 2 to 4 hours. A characterization of an as-sintered (U,Zr)N specimen prepared according to this procedure is given in the table, which lists a UN specimen prepared according to the same schedule for purposes of comparison. TABLE ______________________________________ UN (U,Zr)N ______________________________________ Chemical Analysis U, wt % 94.50 90.51 N, wt % 5.45 5.51 O, ppm 320 204 C, ppm 400 361 Zr, wt % 3.40 Zr, mole % 8.93 X-ray Lattice Parameter 4.889 4.856 Density, g/cm.sup.3 13.38 13.16 ______________________________________ As-sintered UN and (U,Zr)N specimens prepared as described were placed on tungsten plates in a cold-wall vacuum furnace. The specimens were heated at 1600.degree. C. under a vacuum of 1 .times. 10.sup.-5 torr for a total of 8 hours, with intermediate weighings after 1 and 4 hours. The test temperature was then raised to 1700.degree. C. at the same pressure for an additional 8 hours with similar intermediate weighings. The results of these tests showed that at 1600.degree. C. the rate of weight loss of the (U,Zr)N sample was about half that of UN, and at 1700.degree. C. the (U,Zr)N was about three-fourths that of UN. The pure UN sample dissociated to the extent that it sintered to the tungsten filter plate after only 1 hour at 1600.degree. C. An examination of the microstructure of the UN sample showed the presence of free uranium metal. After the additional 8-hour treatment at 1700.degree. C., the UN sample contained extensive free metal distributed throughout its volume while the (U,Zr)N sample showed only slight traces limited to the surface of the sample. Extended thermal testing of the samples was conducted at 1600.degree. C. under a pressure of 2 .times. 10.sup.-6 torr for a period of 100 hours. Both UN and the (U,Zr)N samples decreased in dimension, weight, and bulk density (about 2%). The weight loss of the (U,Zr)N sample was about one-third of the pure UN, indicating a significant increase in thermal stability. In the foregoing specification and in the claims, the novel and improved composition is designated (U.sub.x Zr.sub.y)N and is meant to be understood as involving a composition of 50% nitrogen and 50% metal atoms where x and y indicate the relative concentration of metal. Oxygen and carbon concentrations should be limited to levels which avoid second phase formation. This is particularly true of oxygen where concentrations greater than 0.1% (1000 ppm) may create UO.sub.2 or oxynitride-containing phases. Generally speaking, oxygen-containing phases result in reduction of thermal conductivity, swelling in service, adverse reaction with alkali metal coolants, as well as enhanced plasticity and volatility of relatively volatile UO forms. Soluble carbon concentrations up to 1000 ppm (0.1% C) can be tolerated to a greater extent since none of these potential drawbacks exist with carbon. The scope of and advantages of the claimed composition should be also understood to include Pu as part of the metal component and UN phase in fuel compositions designed for use as fuel in fast breeder reactors designated as (U,Pu,Zr)N. For breeder reactors operating on the U-233 breeding cycle, the (U,Zr)N compositions can accommodate thorium as part of the metal component as (U,Th,Zr)N compositions to realize the enhanced thermal stability provided by the zirconium contribution.