Technical report. Three extractions of a diethyl ether solution of uranyl nitrate with small portions of water are effective in removing rare earths, as is shown by radio-gadolinium and radio-europium tracer experiments. A study of representative ethers, alcohols, ketones, and esters showed that diethyl ether and a mixture of 85% ethyl methyl ketone with 15% xylene are the best solvents for the extraction.

Technical report. Photomicrographs showing the effect of heating polished uranium surface at 600, 700, 850, and 1000 degrees C, and sandblasted and cut surface at 1000 degrees C are included.

Technical report that information has bee obtained on the effect of beta and gamma radiation on the electrical resistance of insulating materials The results are summarized. The recovery to original resistance values has been measured. In general, the initial rate is rapid for the first few hours; the rate then decreases sharply. Certain samples show evidence of complete recovery. Effects on mechanical properties of several plastics has also been studied. Data on gas evolution from several organic materials including those suggested by the physiological shield have been extended to include both beta and deuteron bombardments. Samples of "Press-wood" are being evaluated. The effect of current on the H2O2 production in water containing I- has been studied at several I- concentrations. Water contain-dissolved CO2 shows the presence of oxidant (presumably H2O2). H2O2 has been produced by recoil protons from the scattering of fast neutrons in de-oxygenated water. Radioactive solutions do not greatly affect the applicability the glass electrode providing the electrode is thoroughly washed with distilled water before immersion in the standard buffer solution.

Abstract. The precipitation of Pa233 with MnO2 from a solution of thorium nitrate has been studied in some detail and seems quite satisfactory up to 36 gm Th(HO3)4 4H2O per 100 cc solution. The concentration of Pa233 with respect to the manganese dioxide carrier and the thorium precipitated with the carrier appears to be accomplished quite well by either a series of MnO2 cycles or thorium iodate cycles. Volatility methods for both the separation of Pa233 from the original thorium and for its separation from MnO2 are now under investigation. It has been decided that thorium carbonate will the the thorium compound used in the pile at Site X.

Technical report listing the errata for pages 2, 4, 5, 6, 7, and 8 for report CC-918.

Technical report: The apparatus for the low pressure combustion method of determining carbon in iron and steel has be redesigned to increase the speed of manipulation. It has been tested by running several thousand determinations and found to yield results in good agreement with Wooten's form of the apparatus. A detailed description of the equipment and its manipulation is given together with an account of experimental studies on the method. Results are also shown for the carbon content of copper.

Technical report describing a gasometrical method for the determination of H2 in extruded U rods.

Abstract. A review of all work on uranium hydride published in the CC, CT, CN and CE reports to January 1, 1944, is presented. Some additional information not yet published has been included, so this report includes all data known from the above sources and at Ames to the above date. This report supersedes all previous report on uranium hydride coming out of the Ames laboratory.

Technical report summarizing our knowledge of the chemical effects of ionizing radiation upon water and upon aqueous solutions of inorganic compounds. The types of radiation considered are beta rays, gamma and X rays, and heavy particles, notably neutrons, deuterons, alpha rays and fission recoils.

Technical report covering (1) analysis of uranium bromide and chloride samples, (2) the ferric-nitrate method of analyzing uranium fluorides for fluorine, (3) spectrographic determination of boron, cadmium and manganese in magnesium metal, (4) service analyses. contributions to other problems, (5) attempted preparation of uranous oxyfluoride, and (6) corrections in previous reports.

Technical report abstract: Since UNH is a highly dissociated compound which ionizes to NO3 and (UO2), the latter ion being very weakly basic, a solution of pure UNH is quite acid (pH about 3). It is possible to titrate to a phenolphthalein and point with standard caustic solution and obtain a figure which represents the free acid plus the NO3 from the the UNH. However, titration of the free nitric acid alone in such a solution presents quite a problem. By precipitating and removing uranium from solution by means of potassium ferrocyanide, the residual free acid may be titrated directly by means of standard caustic using either methyl red or phenolphthalein indicators, with an error of less than 4%. A method is given to determine formic acid, should that acid be present in the mixture.

Technical report with short reports on (1) Heavy water analysis and standardization, and Specific gravity of pure D2O; (2) Homogenous exponential experiment; (3) Recombination of pile gases; (4) Slurry pumping studies; and (5) Electron microscope laboratory.

Technical report. Areas covered are properties of uranium halides, properties of uranium nitrides, and hydride formation at high pressure.

Technical report describing the investigation of the short-lived activities produced in oxygen compounds by irradiation with pile neutrons. The most prominent of these activities in cooling water is a beta and gamma emitting activity of about 8 second half-life. Because of its production by epicadmium neutrons it was believed to be the 8 second N16 produced in the pile by n,p on O16. The identification has been accomplished and it is established that the 8 second activity is N16. Part 2 of the report deals with the determination of the recoil range of the Al28 atoms formed by pile n,p reaction on Al27.

Technical report. Long-time tests have been made on the effect of various types of radiation on the corrosion of 2S aluminum in simulated W water. In no case was any acceleration of corrosion by the radiation observed; the effect of radiation, if any, appeared to be a protective one. Deuteron irradiation did accelerate the corrosion of mild steel at low flow rates in hot water of pH 6 to 7, but no appreciable effect was observed with copper, stainless steel, or tuballoy. The general theory of the effect of radiation on corrosion is discussed, with the conclusion that no acceleration of corrosion by radiation is to be expected in most cases of practical interest.

Technical report. The effect of temperature during pile exposure on the fast-neutron-induced change in properties of graphite was studied. Temperatures up to 125 degrees C have no effect upon the rate of increase of elastic modulus; pieces exposed at 300 degrees C on the other hand show no change at all in elastic modulus. The increase in electrical resistance s an inverse function of the temperature of exposure at all temperatures in the range 60 to 300 degrees C.

Technical report with short reports on (1) P-9 recovery from UO2F2 solution; (2) Correlation of theories on action of radiation on matter; (3) Literature surveys on organic compounds and on chemistry of UO2F2; (4) effect of radiation on organic compounds; and (5) Effect of radiation on 100 area construction materials.

Technical report abstract. The present state of knowledge concerning the effect of pile radiation on a variety of solid materials is reviewed. Radiation corrosion will not be a serious hazard for aluminum or stainless steel but it can be for iron or lead if either are exposed to water. Apart from corrosion the principal uncertainty is in regard to the Wigner effect on the behavior of metals. There is at present no ground for optimism regarding the behavior of tuballoy. The effect on aluminum or a bonding material while less severe must also be considered serious. The expectation in regard to graphite is that its behavior will not cause trouble during the first 100 days of operation although serious troubles will probably arise within two years of operation. Organic materials can be used safely only in regions of limited exposure.

Technical report. Quite pure anhydrous ThCl4 in small quantity (8-10 g charge) has been prepared by the action of a mixture of Cl2 and CCl4 vapor on ThO2 at 675 degrees to 725 degrees C.

Technical report containing short reports on (1) Mass spectrometer studies; (2) Purification of heavy water; and (3) Equilibration studies.

Abstract. the electrodeposition of uranium metal, in the form of tree-like deposits, from molten strontium halide baths is described. Under the best conditions studied, approximately 40% recovery is attained. Freedom from side-reactions of the reduced uranium with anode products and/or refractory materials, and high cathode current densities appear to be essential to the success of the process. the refining of uranium under similar conditions appears to occur quite readily, with approximately 50% current efficiency. The preparation of UI3 is also described.

Technical report abstract. A rapid procedure for the preparation of very pure carrier-free Zr and Nb tracer involves the chloroform extraction of the cupferrides of Zr and Nb activities from process solutions. Zr and Nb form very stable chloroform soluble cupferrides in acid solutions (CK-993) and are separated from other fission elements almost quantitatively to yield pure mixture of Zr and Nb activity. A minimum of operations is required and the method is easily adaptable to remote control.

Abstract. In addition to the hexagonal and monoclinic bismuth phosphate precipitates, whose structures are now known, a third crystalline phase has been found to appear in BiPO4 precipitates after (a) extremely long digestion in concentrated nitric acid; (b) oven drying at 800 degrees to 1000 degrees. Thought very small single crystals of the component have been isolated, nor crushed sample contained less than 30% of the beta-form. The cell size and symmetry of the crystal indicates that there ae two bismuth atoms in the cell, and there is no evidence that the compound is not BiPO4. It is suggested that this maty be a third form of BiPO4, stable over a short range of conditions, and tending to revert to the beta-form.

Abstract: Pure UO2F2 is made by reaction between anhydrous HF and pure UO3. Although it is difficult to prepare free of water, it is not very hygroscopic. Prolonged heating at 100-105 degrees releases 99.9% of the water in an aqueous solution; the rate of loss of water is very small after saturation is reached. X-ray diffraction data give a density of 6.2 for the solid. The density of a 1.004 M solution is 1.274; the density of a saturated solution (5.130 M) is 2.400. The densities of F-9 solutions have been calculated from the densities of ordinary aqueous solutions, and the values are compared graphically. Data on the solubility indicate that there is a small increase in the range 25-100 degrees. Recovery of pure F-9 from a solution is hampered by hydrolysis of U)2F2 to give HF. The HF may be held back by addition of UO3 or CaO; the use of the latter, however, makes more difficult the recovery of all the F-9. Molar conductivities of UO2F2 solutions at 25 degrees, as well as the specific conductivities of a 1 molar solution containing various concentrations of UO3, have been determined. The addition of UO3 lowers the conductivity. The low …