Patent Number: 049903039
Section: description

DETAILED DESCRIPTION The numeral 10 generally indicates a fuel element constructed according to the principles of the invention for use in a nuclear reactor. The fuel element includes a zirconium-tin alloy cladding tube 20, a boron-containing glass compound coating or sol-gel residue 30 on the inside of the zirconium-tin alloy cladding tube and pellets 40 of fissionable materials such as UO.sub.2. Lithium or sodium methoxide is dissolved in methanol, with a typical weight ratio of 1:20, by stirring in a closed container. Then a mixture of tetraethoxysilane and acidic aqueous solution (nitric acid (HNO.sub.3) in a 5 to 7, typically 6, weight percent concentration) is added to this lithium solution. The mole ratio of lithium or sodium methoxide to tetraethoxysilane is around 6:1. A reflux of the solution will be performed at a temperature range of 50-80.degree. C. (typically 70 .degree. C.) for a few hours, typically four, to achieve a partial hydrolysis of tetraethoxysilane. The mole ratio of water to tetraethoxysilane is 6:1. Now, tri-n-butylborate with is added slowly to the pre-hydrolyzed solution with constant stirring. (B.sup.10 makes up substantially all of the boron in the tri-n-butylborate.) Another reflux of the solution will be carried out at a temperature range of 50-80.degree. C. for a few more hours, typically four. Before the application of coating, the solution may be further diluted with 2 volume parts of methanol to approximately 1 volume part of solution, depending on the coating thickness requirement. The coating may be applied in any convenient manner; a multiple application may be needed for a thick coating. Other factors for controlling the coating thickness are the rates of application, viscosity of solution, and temperature. At the completion of coating, a heat-treatment of coated sample at 100-150.degree. C., (typically 125 .degree.C.) is performed in an oxidizing atmosphere to drive off volatiles. Then the completion of hydrolysis is accomplished at 200-250.degree. C. (typically 225.degree. C.) in a humid atmosphere. A subsequent heat treatment around 300 .degree. C is for burn-off of unreacted organics. After a final heat treatment at 400.degree. C., the preparation of B residue or coating on the Zircaloy tube is completed. The coating process as illustrated in FIG. 2 includes a process by which the liquid sol-gel is pumped upward into the cladding tube 10 while the tube is in the vertical position. The schematic arrangement of FIG. 2 shows that the hollow tube 10 is attached at its lower end by means of a hose and valve connector apparatus 50 having a valve 52 at the lower end of the tube 10 and a valve 54 adjacent its inlet port from a source of the liquid suspension. The connector 50 has a drain 56 between the two valves 52 and 54. A source of the liquid suspension schematically illustrated as a container of liquid 60 has a valve 62 connected by a conduit 64 to the connector 50 through its valve 54. A tube 68 provides a source of high pressure argon or other suitable gas pressurize the container 60 of the liquid suspension. the over-pressure of argon gas is used to pump the liquid up the tube 10 with the valves 62, 54 and 52 open. Air is exhausted from the tube 10 through an upper vent tube 66. The liquid suspension is held in the tube 10 by means of valve 52 approximately 1 minute. The liquid is then drained at a controlled rate manually controlling the valve 52. A rapid drain rate would result in the formation of a very thin coating, whereas the slower drain rate would produce coatings that would be thick and more irregular. The tube 10 is made of a zirconium-tin alloy which is commonly called Zircaloy-2 or Zircaloy-4. The compositions of Zircaloy-2 and Zircaloy-4 are shown in Table I, but it should be realized that each will contain some other impurities within tolerance limits known to those skilled in the art. Table I shows the alloying constituents and it should be remembered that the remainder is zirconium and that all ranges are given in percent by weight. Thus, it will be seen that the invention provides a nuclear fuel element having a burnable poison coating or residue in the form of a thin layer of boron-containing compound particles on the inside of the cladding tube in a manner which provides a matched thermal expansion coefficient between the cladding tube substrate and the coating to prevent spalling and which provides an adhesion promoting sintering phenomenon from the irradiated environment. The use of these improved elements eliminate the requirement of displacing fuel rods within the assembly lattice and therefore minimizes the fuel material that is displaced in the nuclear reactor core. TABLE I __________________________________________________________________________ ZIRCONIUM-TIN ALLOY (% BY WEIGHT) Zircaloy-2 Zircaloy-4 Range Typical Range Typical __________________________________________________________________________ Tin 1.20 to 1.70 1.55 1.20 to 1.70 1.53 Iron 0.07 to 0.20 0.14 0.18 to 0.24 0.22 Chromium 0.05 to 0.15 0.08 0.07 to 0.13 0.10 Nickel 0.03 to 0.08 0.06 -- -- Niobium (columbium) -- -- Oxygen A A A A Iron + chromium + nickel 0.18 to 0.38 0.28 -- 0.32 Iron + chromium -- 0.28 to 0.37 __________________________________________________________________________ The remainder is zirconium and impurities within tolerable amounts.