The cyclotron is the only practical source of many carrier-free radioisotopes. The preparation and radiochemical isolation of a number of these activities, produced in the 60-inch cyclotron of Crocker Laboratory, will be presented in this paper and in subsequent papers of this series. In most cases the carrier-free radioisotopes were prepared for use in biological systems and the final preparations were in the form of isotonic saline solutions at a range of pH from 5 to 8. The present paper reports the radiochemical isolation of carrier-free Sn{sup 113} and In{sup 114} produced by bombarding cadmium with 38 Mev alpha-particles. At this energy, Sn{sup 113} and In{sup 114} are produced in a thick target by the nuclear reactions; Cd{sup 110}({alpha},n)Sn{sup 113}, Cd{sup 111}({alpha},2n)Sn{sup 113}, Cd{sup 112}({alpha},3n)Sn{sup 113}, Cd{sup 111}({alpha},p)In{sup 114}, Cd{sup 112}({alpha},pn) In{sup 114}. The shorter-lived tin and indium activities together with the possible radioisotopes of silver produced by (n,p) reactions, were allowed to decay out prior to the chemical separations.

The progress report discusses activities of the P Division for the month of July, 1949. The B and F piles operated at 275 megawatts and the D pile at 305 megawatts throughout the month except for outages listed under Area Activities. A total of 57.5 tons of metal, at an average concentration of 363 megawatt days/ton (MWD/ton) was discharged from the piles during the month. This included 41.9 tons of Class V (alpha-rolled, triple-dipped, completely transformed) metal at an average concentration of 397 MWD/ton which was discharged without difficulty. A portion of this material was inspected and appears to be satisfactory for exposures at this concentration.

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The pile physics group reports on reactivity power coefficients from the production test No. 105-248-P, the water leak in B pile, graphite properties, xenon equations from the B pile shutdown of March 1946, and reactivity balance. The experimental physics group headed by J.M. West reports on graphite testing, the P-11 project, and shielding. The experimental physics group headed by E.B. Montgomery reports on diffusion length measurements in the DR and H piles. (GHH)

The redox and pile operations are reported on. Construction in 100 (Pile), 200 (Separation), and 300 (Metal Fabrication) areas is described. General work in the Richland commercial areas and on the Southern Railroad connection is also described. Personnel information is disclosed.

The available information on the ionic and radiochemical composition of current and aged bismuth phosphate process wastes is tabulated here for the convenience of those concerned with metal recovery. In addition to its application in the design of research and development experiments, the compilation may serve to suggest specific needs for additional analytical data. For convenience in chemical calculation, molar compositions have been calculated for the ionic constituents based on the g/1 values usually reported. The dates of radiochemical analyses required for decay calculations should be available from the Analytical Sections at ORNL and HW.

On June 29th and July 13th, 1949, the Industrial Hygiene Group of the Health Instrument Divisions at HAPO conducted a study of the health aspects of the degreaser operations carried on in the Airlock adjoining the 105 Building in the 100 H Area. This was done at the request of the Medical Division. The results of the study, together with certain pertinent information concerning degreaser operation, are reported in this report.

A potential source of dangerous concentrations of hydrogen cyanide exists in the plating room of the Machine Shop where open plating baths containing cyanide salts are maintained and where solid cyanide salts are stored. Also the use of hydrogen sulfide in certain steps of the waste disposal process has lead to noticeable and sometimes objectionable concentrations of this gas in the air of the "WD" Building. In view of the toxic properties of these two gases, it was desirable to set up suitable tests to determine the actual concentrations present in the air of the respective working areas.

The general principles of a liquid-liquid solvent extraction method for the separation of metallic elements are outlined.

A high resolution scale-of-four has been developed to be used in conjunction with the nuclear particle detection devices in applications where the counting rate is unusually high. Specifically, it is intended to preceed the commercially available medium resolution scaling circuits and so decrease the resolving time of the counting system. The circuit will function reliably on continuously recurring pulses separated by less than 0.1 μ sec. It will resolve two pulses (occuring at a moderate repetition rate) which are spaced at 0.04 μ sec. A five-volt input signal is sufficient to actuate the device.

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Experimental results on the adsorption of U from solutions by activated C indicate that low pH values reduce the adsorption and that a marked change occurs in the adsorption of U(VI) at pH2. Under a given set of conditions the adsorption of U follows a typical Freundlich isotherm. The particle size of the charcoal affects the rate of adsorption but not the amount of U adsorbed at equilibrium. The temperature coefficient of adsorption is negligible, and the adsorption of U from uranyl solutions is a reversible process. (BJH)

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Experimental use of sodium radiophosphate (P32)in treatment of polycythemia is described. Treatment history is 66 patients treated with P32 alone, 32 patients treated with P32 followed within 4 months by venesections, 21 patients treated with P32 followed more than 4 months later by venesections, 6 patients treated exclusively by venesections, and 9 patients treated and followed elsewhere.

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