The commercial feasibility of the electrolytic process for Th production has been demonstrated. The cell produced 7 lb. of good quality metal per hour. A cathode cooling system was developed. The major construction materials, Ni and graphite, were satisfactory. The process yield was 86%. (T.R.H.)

A description of hot laboratory metallography and techniques of operation are presented. These facilities and techniques provided a means of examining fuel elements that contain UO/sub 2/ after irradiation to high burnups. Some unusual irradiation characteristics of UO/sub 2/ were observed, and each effect is discussed. A complete explanation of the causes of such effects has not yet been obtained. (auth)

It is deemed feasible to store reactor fuel wastes in a salt dome cavity to a depth where the differential in pressure between the soil over-burden pressure and pressure of the fluid inside the cavity does not exceed 3000 psi, and the temperature is less than 400 deg F. Tests at pressure increments of 1000 psi were conducted on a 2" cylindrical cavity contained in a 6-in. long by 6-in. cylindrical salt core. Tests indicate that the cavity exhibited complete stability under pressures to 3000 psi and temperatures to 300 deg F. At temperatures of 100 to 400 deg F and pressures to 5000 psi continuous deformation of the cavity resulted. Initial movement of the salt was observed at all pressures. This was evidenced by vertical deformation and cavity size reduction. It was noted that a point of structural equilibrium was reached at lower temperatures when the pressure did not exceed 5000 psi. A literature study reveals that the most common type of cavity utilized in liquefied petroleum gas storage is either cylindrical or ellipsoidal. A few are pear or inverted cone shaped. There was no indication of leakage for cavities when pressure tested for as long as 72 hr. …

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Solid phases in the zirconium-nitric acid-hydrofluoric acid system were identified by chemical and x-ray diffraction methods. Five different compounds were crystallized at various temperatures and fluoride concentrations from fluoride or fluoborate solutions. These include the mono- and trihydrates of zirconium tetrafluoride, plus three hydrolysis products which possess a fluoride- to-zirconium ratio of approximately three, yet produce different x-ray patterns. The trifluorides crystallize from solutions of low fluoride-to-zirconium ratio at temperatures of below 90, 65 to 100, and above above 95 deg C, respectively. Solubilities of these basic trifluorides were measured at 25 deg C in 1, 6, and 16M nitric acid. (auth)

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The purpose of the research work presented in this volume is to develop a process for the separation and purification of actinium-227 produced by neutron bombardment of radium-226 and to develop methods by which uniform films of actinium metal may be deposited on metallic surfaces. The design work on the cave structure and mechanical equipment used in the actinium separation is proceeding on schedule. As the mechanical design phase is nearing completion the emphasis is being directed toward processing equipment. The process as well as the mechanical equipment has been adapted from the research work of F. T. Hagemann and the Remote Control Group at Argonne National Laboratory. Consequently, one of the first objectives is to become familiary with the chemistry of the process and the operation of the mechanical equipment. Cold runs have been made on the T.T.A. benzene extraction using lanthanum and barium in place of actinium and radium. No difficulty with the operation was observed. The formation of precipitates was one of the difficulties encountered with the process as the precipitates carry radium. It has been found that metals such as nickel cause these precipitates to form and should, therefore, be avoided in the construction of equipment. …

The purpose of the research work reported in this volume is the development of a process for the separation and subsequent purification of radium from the K-65 (pitchblende) residue. Except for the accumulation of additional experimental data the process is essentially complete. After a preliminary extraction of about 85% of the lead and 40% of the silica with a 40% sodium hydroxide solution, the residue is treated with a solution containing both sodium hydroxide and sodium carbonate to obtain additional lead removal and partial conversion of the radium and barium sulfates to carbonates. After leaching out the soluble carbonates, the residue containing unconverted sulfates is treated with a sodium carbonate solution at 170{sup o} under pressure. A study of the amount and concentration of sodium carbonate required to obtain a satisfactory conversion of the sulfates has shown that the total sodium carbonate may be reduced by 40% and that smaller volumes of solution may be employed without serious decrease in the efficiency of the conversion. In order to make calculations on the number of steps and tank sizes for the radium-barium separation by fractional precipitation, equations have been developed to calculate this information from the theoretical separation factors determined experimentally. …

This quarterly report details activities of chemical research by the Separations Technology Unit for the months of October, November, and December 1951.

The possibility of evaluating experimentally the effects of locally applied medications on the rate of burn healing was explored. Twenty or 24 small burns were produced on each of eight anesthelized Chester White pigs by an exposure of 10 calories per square centimeter delivered ln 3 seconds. In earlier studies it had been found that lesions from this exposure are moderate second degree burns which, if untreated, are completelly covered wiih new epithelium in 14 days. Nine days after injury, less than half of them exhibit this degree of healing. The five medicated ointments tested were applied to randomized burns once a day for five days. After four days without treatment, the burns were biopsied. The degree of epithelial coverage was evaluated microscopically, and the results in treated and untreated areas were compared. None of the medications significantly promoted or delayed epithelial regeneration. Variations in healing rate from one animal to another and in different anatomical locations on the same animal were noted. These findings should affect the design of any experiment to determine the effects of treatment on healing. (auth)

A review of data on the effects of chlorides in nitric acid solutions upon stainless steel indicates that the proposed maximum chloride specification of 350 ppm chloride in the Darex Pilot Plant product is reasonable. (auth)

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This report addresses the density-weight percent molarity conversion equations for Uranyl sulfate-water solutions at 25°C and between 100-300°C.

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This report addresses the corrosion of zirconium in 600°F water and in 750°F superheated steam.

A parameter study was made of some of the nuclear characteristics the HRT would have if the core and blanket were operated at different temperatures. The power density in the fuel solution at the inner surface of the core tank was found to be affected very little by the temperature distribution. However, the thermal flux at the core-tank wall increased when the blanket temperature was reduced (a consequence of the reduced critical concentration). (auth)

The status of the overall design, fabrication, and installation of the component items of the PAR loop experiment in the ORR is reviewed.

Tests have been made to determine the sensitivity of various radiation detection instruments for known amounts of ThO/sub 2/ contained in simulated cuts and abrasions. A shielded Geiger-Mueller counter tube can be expected to detect at least 0.1 mg ThO/sub 2/ when counting for a reasonable length of time provided the ThO/sub 2/ deposit is on the surface of the subject being counted. A shielded gamma-spectrometer-crystal, set at a 50-kev cutoff, can be expected to detect at least 0.5 mg ThO/sub 2/ even when an absorber equivalent to 1/2 in. of paraffin is placed between the crystal and the ThO/sub 2/ sample. Duration of exposure of standard film badge photographic emulsions is inversely proportional to the amount of material present and an exposure of about 300 hr is required to detect 10 mg of surface ThO/sub 2/. Although no information is available on the amount of thorium required to induce fibrosarcomas, an extrapolation of data for plutonium indicates that of the order of 1/2 gram of thorium must be present before occurrence of fibrosarcomas would be observed. This value does not represcnt a lower limit but is more likely to be a value for which occurrence of fibrosarcomas are a …

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This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for December 1957.