Patent Number: 042319765
Section: summary

BACKGROUND OF THE INVENTION 1. Field of the Invention This invention concerns a process for the production of ceramic plutonium-uranium nuclear fuel in the form of sintered pellets made from a fine-grained starting material containing plutonium and uranium as oxide, carbide or nitride. 2. Description of the Prior Art In the production of ceramic nuclear fuel, i.e. ceramic material from uranium, plutonium or thorium, or mixtures of these metals, or solid solutions of such mixtures of metals, wherein all components are present in the form of oxides, nitrides or carbides, conventionally the usually cylindrical fuel pellets are obtained by sintering pressed "green powders", as this is described, e.g., in "Nuclear Energy Maturity. Proceedings of the European Nuclear Conference Vol. 7 `Fuel Fabrication`. Progress in Nuclear Energy, Pergamon Press (1976)". In the case of plutonium-containing fuel, as, e.g., uranium with about 3% plutonium for the production of oxide for use in a Light Water Reactor (LWR) Pressurised Water Reactor, PWR), Boiling Water Reactor (BWR) or Advanced Gas-cooled Reactor (AGR), or uranium with 10-14% plutonium in the form of mixtures of oxide, carbide or nitride for use in a Fast Breeder Reactor (FBR) cooled with liquid sodium or a gas, it is usual to blend the two pulverulent components which separately contain the uranium and plutonium in the form of oxide, or to mix the uranium oxide and the plutonium oxide together with finely divided carbon in order to obtain the carbide and the nitride. From these starting powder mixtures cylindrical green pellets in hydraulic or mechanical presses are pressed. The green pellets are then baked in order to result in a dense sintered pellet. In the case where in the manufacture of the green pellets the oxide was mixed with carbon, a preliminary heating step may be interposed before the baking during which the carbon reacts with the oxides of plutonium and uranium and forms the carbide. The thus obtained carbide material is then granulated by comminution and ground and finally, as before, pressed and sintered in order to obtain the required final density. The final sintering used with green pellets mixed from oxides or with the re-shaped carbide pellets is important for the manufacture of dense pellets with a homogeneous distribution of plutonium in the uranium structure. This homogenisation takes place by self-diffusion and is necessary so that no localised regions of above average plutonium concentration should occur. The good sintering properties required for achieving a high final density and a complete diffusion of the plutonium in the uranium matrix are dependent on the characteristics of the powder forming the initial mixture, such as particle size, particle surface, particle shape, flowability and the quality of the mixture itself. In order to obtain sintered pellets of high quality, the uranium or plutonium oxide powder with or without carbon, or the separately won powders of uranium and plutonium carbides must be ground optimally and mixed extremely carefully. In certain cases, the final grinding and the mixing of the powders are undertaken in a single process step while in other cases the powders are first ground to the required quality and then mixed. The grinding and mixing of plutonium-containing powders give rise to difficulties. Because of its toxicity, its radioactivity and the danger of ingestion, plutonium material can only be handled and prepared under the strictest controls in a sealed room, such as a radiologically protected room or in an .alpha.-tight cell. Some industrial nations have issued fabrication guidelines for the production of plutonium-containing fuels which comply with the above-mentioned principles. In the manufacture of ceramic fuel pellets, it is particularly the plutonium-containing dust arising in the preparation of the powder that leads to special difficulties, because without special precautionary measures the operating personnel receive, or could receive, impermissibly high radiation doses. Such radiation fields are also caused in part by a byproduct of plutonium, namely americium, which emits hard gamma rays and can cause a direct irradiation of the service personnel or the maintenance personnel through the dust which coats the apparatus and the interior surfaces of the radiation-protected rooms into which latter personnel must from time to time enter in protective clothing for the maintenance of apparatus. Further difficulties are caused by lost plutonium, i.e., plutonium adhering to surfaces and retained in the filters. It is anticipated that these problems will increase, particularly because of the increase in the radioactivity of plutonium caused by the longer residence time (higher burn-up) in "producing" reactors, to which one should then still add the spontaneous neutron emission (spontaneous fission) of Pu-238 (.alpha., n) and the gamma emission of plutonium 236 (.gamma.) which increases with increasing recovery of plutonium materials. Spherical fuel particles may be produced in wet chemical processes. Of these, the most important are: The Sol-gel process which has been described, e.g., in: (L1) Proc. Panel for ceramic nuclear fuels, 6-10 May 1968 Vienna, IAEA PA1 "Sol-gel processes for ceramic nuclear fuels"; PA1 (L2) U.K. Patent Spec. No. 1,175,834 (24.12.1967) "Improvements in or relating to the chemical production of metal containing materials as particles or other configurations" and PA1 (L3) Julich Report, Jul. 1229, 1975; PA1 (L4) German Patent Spec. No. 2,059,093 "Process for the production of spherical particles which contain a metallic oxyhydrate, metallic oxyhydrate with carbon . . . , from an aqueous solution" and in PA1 (L5) Forthmann R. et al, in Jul-655-RW (April 1970) "Investigation on the preparation of UO.sub.2 microspheres by internal gelation of a UO.sub.2 sol and from a uranium (VI) solution", and PA1 (L6) Stratton R, and Bischoff K in Op. cit ref. 1, vol. 3 "The mixed carbide fuel programme at EIR". PA1 (i) a mixture of (a) an oxide, finely divided carbon-containing oxide, carbide, nitride, oxycarbide, or carbonitride of plutonium, in the form of microspheres obtained by a wet chemical process, and (b) a like compound of uranium in a form selected from such microspheres and fine-grained to pulverulent materials; or PA1 (ii) a like compound of a plutonium-uranium solid solution of which at least 1% is plutonium, in the form of microspheres obtained by a wet chemical process, alone or in admixture with a material selected from the said plutonium-compound microspheres, the said uranium-compound microspheres and the said fine-grained to pulverulent materials, The precipitation process, known from: The internal gelation process, described in: The EIR carbide process which is described in These wet chemical or gelation processes may all be used for the purpose of directly obtaining ceramic sintered material from uranium and plutonium, i.e. without grinding, mixing and powder pressing, in the form of microspheres of oxide, carbide, carbide or nitride for use as fuel in reactors. Such a special process is described e.g. in Swiss Patent Specification 581,890 (REACTOR CENTRUM NEDERLAND) "Process for converting a spherical sol-gel fissile material by sintering to a spherical nuclear fuel material containing oxide, carbide or carbonitride". Accordingly, ceramic uranium-plutonium nuclear fuel is available in the form of microspheres producible by a wet chemical method or in the form of sintered pellets which latter are significantly more advantageous in use than microspheres but the manufacture of which is difficult and has problems that can only be solved by corresponding expenditure. SUMMARY OF THE PRESENT INVENTION Accordingly, the task of the invention is to find a better process for the production of sintered pellets from ceramic uranium plutonium nuclear fuel wherein the above-described difficulties are mitigated and which makes it possible to produce uranium-plutonium sintered pellets in a manner which is advantageous in other respects also. The solution of the task consists according to the invention in a process for the production of a plutonium uranium ceramic fuel wherein green pellets are formed by pressing from: and the green pellets are subjected to a heat treatment that includes a sintering to final density. Since in the process according to the invention, the plutonium remains in liquid form until that stage of the process in which the microspheres are formed, and in the known gelation processes the microspheres may be obtained in the correct size via the feed nozzles used in such processes, grinding of the plutonium containing particles to their optimum size is no longer necessary. The microspheres obtained by a wet chemical process are only subject to processes such as washing, drying, mixing, pressing and sintering until the end-product of the ceramic plutonium uranium sintered pellets is obtained, which processes are either dust-free or are at most low-dust processes wherein plutonium losses are also significantly reduced. In this way, the drawbacks associated with conventional production processes are eliminated in a direct way. In addition, the process according to the invention affords still further advantages which among others and above all are of significance in obtaining ceramic sintered pellets of high quality, such as: the particles to be processed are available in the form of microspheres which, because of their particularly good flowability, may be mixed easily so that the required homogeneity of the mixture is ensured; the wet chemical production of the starting material particles makes it possible to reduce the americium content of plutonium by chemical separation directly before the fabrication of the fuel elements; the green plutonium particles, or uranium and plutonium particles in the form of a standard mixture, may be produced directly in a chemical reprocessing plant; by a special manner of operating the pelletising process sintered pellets of any arbitrary "low" desired density may be produced. For the production of uranium-plutonium carbide sintered pellets, carbon-containing plutonium or plutonium-uranium microspheres can be produced by a wet chemical route wherein finely divided carbon in suspension is added to the feed solution. In a heat treatment, i.e. of the microspheres, reaction sintering, the carbide is then formed by a carbon-thermal reduction. The plutonium carbide microspheres may be mixed with the uranium carbide microspheres or with fine-grained to pulverulent uranium carbide in such a ratio that the desired final content of uranium and plutonium is obtained in the sintered pellets. DESCRIPTION OF THE PREFERRED EMBODIMENTS The following graphical representation schematically shows as examples of embodiment four different routes by which according to the process of the invention, sintered pellets of mixed uranium-plutonium oxide, a mixed carbide or a mixed nitride are obtained from starting materials. From sols, suspensions or solutions of uranium and plutonium, which may contain finely divided carbon, xerogels in the form of microspheres are produced according to the known sol-gel process wherein here and in what follows the final product of the wet chemical process is to be understood by the term "xerogel". The starting material for the plutonium component consists exclusively of such xerogels while the starting material for the uranium component may consist of xerogels or of a fine-grained to pulverulent material. ##STR1## Route I One starts with a uranium-plutonium xerogel which contains finely divided carbon for the production of carbide pellets in the microspheres. The xerogel microspheres are pelletised and the green pellets are calcined in a pre-heating step and then reaction sintering at a higher temperature is undertaken whereby to bring the production of sintered pellets by this Route I to its conclusion. Route II: One starts with microspheres of a plutonium xerogel, and with microspheres of a uranium xerogel, or with a fine-grained to pulverulent uranium material, both types of particles being with or without carbon. The two types of particles are mixed together in a quantity ratio which corresponds to the desired uranium and plutonium content of the finished sintered pellet. Then the particle mixture is pelletised. The obtained green pellets are calcined in a pre-heating step and then subjected at a higher temperature to reaction sintering. Route III: As in the second route, here also the start is from microspheres of a plutonium xerogel and from microspheres of a uranium xerogel or from a fine-grained to pulverulent uranium material wherein the plutonium and uranium materials may contain carbon. If the starting materials are microspheres of uranium and plutonium then the microspheres are calcined, each type separately, and then the calcined microspheres are mixed together in a quantity ratio dependent upon the final product. The microsphere mixture is pelletized and the pellets are subjected to reaction sintering that takes place at a higher temperature. If the starting material is plutonium microspheres and a fine-grained to pulverulent uranium material, then the uranium material is mixed with the calcined plutonium microspheres in the prescribed quantity ratio. The particle mixture is then pelletized and the pellets are subject to reaction sintering. Route IV: The starting materials are once again a plutonium xerogel and a uranium xerogel or a fine-grained to pulverulent uranium material. When microspheres of uranium xerogel are used, which may contain finely divided carbon, and microspheres of a plutonium xerogel with or without carbon, then each type of microsphere is separately calcined in a pre-heating step. The calcined uranium microspheres and the calcined plutonium microspheres are then, again separately for each type, subjected to reaction sintering. The thus pre-sintered uranium microspheres and plutonium microspheres are then mixed as described for the other routes and then the microsphere mixture is pelletized and the obtained green pellets are finally sintered again. When a fine-grained to pulverulent material is used as the uranium component, then either the uranium material that is equivalent to the calcined uranium microspheres is subjected to reaction sintering and then mixed with the plutonium microspheres treated in reaction sintering, or a fine-grained to pulverulent uranium material corresponding to the uranium microspheres treated by reaction sintering is mixed directly with plutonium microspheres treated in the reaction sintering. After the mixing, pelletization and final sintering of the mixture take place. From the initial xerogel, Route I has the fewest process steps, namely only pelletisation, calcining and reaction sintering, wherein the calcining and the reaction sintering follow each other in a heat treatment of the green pellets. In routes II and III mixing is added. Route II begins with the mixing and then takes place as route I. In Route III mixing takes place first only after calcining which is the beginning of this route. In Route IV the initial stages of calcining and reaction sintering may take place during heat treatment in successive steps. After mixing and pelletisation a final sintering is added as a further process step. Naturally, the production of xerogels is also significant. A few examples of embodiment of the process according to the invention are treated in greater detail in what follows.