In the canning operation, the preparation of aluminum components is important in assuring uniform wetting of the aluminum surfaces with Al-Si. The surfaces of the components should be free of dirt and grease and should also have a minimum retention of non-metallic film, normally aluminum oxide, for the best wetting properties. At present, dirt and grease are removed satisfactorily by a vapor degreaser followed by a Duponol-alkaline wash. The standard specified method of removing the aluminum oxide film from aluminum cans is a four-minute etch in twenty percent phosphoric acid. The oxide is removed from the caps by an eight-minute etch in twenty per cent phosphoric acid or an alternate etch of a one percent solution of hydrofluosilicic acid. If the phosphoric acid etch is not controlled properly, it is possible to form a thin, inert phosphate coating on the surface of the aluminum, which is undesirable for good wetting characteristics. In an effort to find a better etchant for aluminum components, an investigation of various commercial and non-commercial etchants was undertaken. This report details results of this investigation.

None

None

A large number of experiments relating to nuclear structure and materialization of energy will fall within the energy range of primary and secondary particles available from the Bevatron. Some experiments of interest are outlined below with pertinent comments. Proton-proton scattering can be extended to the high energy range using liquid hydrogen targets and hydrogenous materials by bombarding the target with the internal beam or using externally scattered protons. Proton-deuteron scattering measurements using liquid deuterium targets or solid materials can also be extended. Proton scattering from heavier nuclei may be found less difficult to interpret at these level energies as the nucleons will interact more or less independently. The wavelength of the bombarding particles will now be much smaller than nucleon diameters. Nuclear collisions represent by far the most important interaction between high energy nucleons and matter. Proton-neutron charge exchange interaction within the internal target will provide an external flux of neutrons which can be used directly for total nuclear cross section measurements and neutron-proton scattering. Low energy measurements, say below 200 Mev; show that nuclear interaction cross sections do not go down as 1/{lambda} as reactions become predominantly nuclear rather than electromagnetic. Measurements can now be extended into the Bev …

None

None

None

The effects of chloride on the design and operation of a HNC/sub 3/-recovery facility are summarized. Data are presented on the concentration gradients of chloride ions in fractionators and absorbers, as well as methods for removal of chlorides to eliminate serious corrosion problems. (C.H.)

None

Power Breeder Reactor. Conceptual design studies for the Power Breeder Reactor indicate the feasibility of a contained primary coolant system in a package arrangement. One- and two-group calculations are presented in detail for preliminary PBR estimations. A technique for impregnating UO/sub 2/ with NaK has been developed. The resulting putty-type fuel was successfully extruded tbrough a 3/8-in. hole. Data are presented on the fuel element design factors imposed by heat transfer and cooling limitations for fuel plates, pins, and spheres. Fission heat liberated in the PBR blanket was estimated to be 7.7% of the total core power. Design criteria resulting from this estimate are analyzed. Heat exchanger size for the transfer of 500 Mw of heat from Na to NaK has been calculated for the intermediate exchanger and for the NaK-toH/sub 2/O steam generator. A theoretical treatment is presented for the thermal stress analysis of stainless steel-clad U fuel plates. Boiling Reactor Heat Transfer Experiments. Further results have been obtained from natural-circulation boiling-density tests and investigations of natural-circulation flow rates. A special thermocouple design, meeting the rapid-response requirements of high-power plate transients, is described. Feasibility studies on heavy water boiling reactors are presented for spherical boiler, pressurized tube, and horizontal …

None

The applicability and refinement of various procedures for the treatment and digestion of C-slags and other uraniferous residues for recovery of U values were studied. The recovery of U from BFC-6 was investigated, placing emphasis on procedures which will not chemically alter the Cu and Sn media. Methods of U recovery from various residues resulting from Na/sub 2/CO/sub 3/ digestion of miscellaneous U-bearing materials, to reduce the U/sub 3/C/sub 8/ content below 0.05%, are discussed. (W.L.H.)

None

None

None

None

None

None

None

None

None

None

None

About twenty-five to thirty per cent of the uranium slugs canned in the Metal Preparation Section do not meet specifications and are rejected. These rejected slugs are recovered by a chemical process and prepared for re-canning. The canning operation provides a coating of metal composed principally of elemental aluminum and silicon with traces of copper and tin, which bonds the aluminum can to the slug. The elements in intimate contact with the slug combine chemically with the uranium to form the tenacious compound layer. The current recovery process consists essentially of a sodium hydroxide-sodium nitrate bath for chemically removing the aluminum can and the bonding medium, followed by hydrofluoric acid and nitric acid baths to remove the remaining compound layer and to pickle the slugs before they are returned to the process canning line. Recent studies have indicated the possibility of using a more economical means of recovery. This includes the mechanical removal of the aluminum can and most of the bonding medium, followed by a chemical removal of the residual compound layer by a solution of sodium hydroxide. A laboratory scale investigation was made to determine whether a solution of sodium hydroxide would remove the compound layer from de-canned, …