A simple mass spectrometer using 60 degree focusing was set up to study the (illegible) of the ions produced by various types of sources. A schematic diagram of the apparatus is shown in Fig. 1, which is to a large extent self-explanatory. The isolation transformer was simply a piece of RG (illegible) cable about three feet long and was used in order to operate the source at high accelerating voltage allowing the collector to be at essentially ground potential. The collimating slits were 0.05 (illegible) wide and were space 4 (illegible-cm?) apart. The coarse slit immediately preceding the collector cup was 0.3 (illegible) wide. The electrometer was the integrating type which indicated the potential due to the charge collected on known capacitance. The vacuum tube voltmeter indicated the potential of the 0.5 (illegible) capacitor due to the total charge reaching the slit system. It thus served as a monitor of the source output for each firing. The neon lamp was a protection for the condenser against breakdown discharges of the tube.

Resting cells of eleven microorganisms were exposed to radioactive carbon dioxide for 40 minutes. The radioactive compounds formed during this time were separated and identified by paper chromatography. Resting cells of Lactobacillus casei fixed no carbon dioxide and growing cells fixed carbon dioxide primarily in malic and aspartic acids. All of the radioactive compounds formed could have become radioactive by reversal of known decarboxylation reactions.

A kinetic product study of the carbonate cleavage of malonic ester has been made, and it is shown that the formation of carbonate from malonic ester in alkaline solution involves the direct fission of the half acid ester.

It seems hardly necessary to repeat to an audience of this kind the importance of the process known as photosynthesis in the interaction and the interdependence of organisms and in the very existence of life as we know it. This process by which green plants are able to capture electromagnetic energy in the form of sunlight and transform it into stored chemical energy in the form of a wide variety of reduced (relative to carbon dioxide) carbon compounds provides the only major source of energy for the maintenance and propagation of all life.

The fission and spallation reactions caused in uranium by bombardment with high energy protons (340 t o 350 MeV) were investigated. The reaction products were separated from the target by chemical processes and identified by their radioactive properties. The relative yields of the observed fission products were measured, and the results plotted as a function of mass number. Several of the spallation products were identified and their yields estimated. An attempt was made to determine the most probable atomic number for a nuclide of given mass formed directly from fission. Studies were made of the relative yields along several isobaric chains as a function of atomic number. From these data predictions of the mass and charge of the fissioning nucleus are made.

The directions for preparing the following acids from labeled acetic acid on a 1 to 20 millimole scale is presented: Succinic acid, malic acid, fumaric acid and tartaric acid. Two methods for preparing the succinic acid are detailed.

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A considerable volume of work was accomplished during the past three months in the tracer program, experiments being conducted with At{sup 211}, carrier-free Bi{sup 206}, carrier-free Mn{sup 52}, carrier-free Mo{sup 93,99}, Np{sup 237}, Ta{sup 182} of a fair degree of specific activity, carrier-free Sc{sup 46}, and high specific activity Tm{sup 170}.

Comparative studies of a series of halogenated solvents, as carriers for TTA in the chelate process for plutonium extraction, indicate that ortho-dichlorobenzene most nearly satisfies the requirements that are set forth. A complete process design is presented for use with this solvent, and flow data and equipment capacities are given for dissolver solution and for uranium-free fission product solution as alternate feeds to the process. Vertical mixer-settlers are recommended as the contractors, although pulsed columns or packed columns are also believed to be suitable. The size of such units is estimated from the best available rate and equilibrium data, and the effects of several operating variable are considered.

It was the purpose of this talk to present up-to-date information with regards to dimensional stabilityof metallic uranium. A brief discusssion concerning the history, present status, proposed theories, and recent results are given. The factors affecting and methods of minimizing dimension changes are outlined.

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This volume is one set of a series which has been prepared as a record of the research work done under the Manhattan Project and the Atomic Energy Commission.

The fused fluoride-Inconel reactor system was studied under irradiation with nominal 19 Mev deuterons as supplied by the Berkeley 60-inch cyclotron. Chemical, metallographic, magnetic susceptibility, electron diffraction and X-ray diffraction studies were made on the as-received materials, one control run and two irradiated runs. No changes in the fused fluoride fuel were noted. Accelerated intergranular corrosion and increased grain size were observed in the irradiated Inconel specimens. This report is based upon studies conducted for the Atomic Energy Commission under Contract AT-40-1-GEN-1064.

A. M. Gaudin and collaborators have published a curve of refining costs versus ore grade in terms of dollars per pound of U308 recovered on the basis of 90% recovery.

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. …

A relatively inexpensive reactor for the specific purpose of testing a sub-critical portion of another reactor under conditions that would exist during actual operation is discussed. It is concluded that an engineering tool for reactor development work that bridges the present gap between exponential and criticality experiments and the actual full scale operating reactor is feasible. An example of such a test reactor which would not entail development effort to ut into operation is depicted.

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Siimplified shielding calculations indicating the proposed design for the water boiler assembly will reduce the radiation at normal operaton to values well below those which are considered tolerable.

Two important problems in the investigation of reactor hazards are the chemical reactivity of various materials employed in reactor construction and the chracteristics of heat transfer under transient conditions, specifically heat transfer when driven by an exponentially increasing heat source (exp t/T). Although these problems are independent of each other, when studied in relation to reactor hazards they may occur in a closely coupled sequence. For example the onset of a dangerous chemical reactor may be due to structural failure of various reactor components under an exponentially rising heat source originating with a runaway nuclear reactor. For this reason, these two problems should eventually be studied together after an exploratory experimental survey has been made in which they are considered separately.

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On 2/8/1950, there was mined from process tube 2273 in D pile at Hanford a quantity of graphite power, which was expected to show the most extensive radiation damage of any graphite available at that time. A series of samples of this powder were annealed in 100 degrees increments from 100 degrees to 2000 degrees C at this labaoratory. There were returned to Hanford and shipped by them to the National Bureau of Standards for total stored energy measurements. The present memorandum is comprised of a description of the annealing procedure used here, curves giving the detailed annealing history of each sample, and various curves derived from data obtained from these samples at Hanford and at the National Bureau of Standards.

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The vapor pressure of bromine trifluoride has been measured over the range 39 to 155 C. and the following equation was derived by methods of least squares to represent the experimental data. log{sub 10}P{sub mm} = 7.74853 - l685.8/(t + 220.57). The heat of vaporization was estimated from the following equation which is based upon the Clausius-Clapeyron relation. {Delta}H{sub cal/mole} = 7714 [(t + 273.16)/(t + 220.57)]{sup 2}. In continuation of the program to measure the physical properties of interhalogens, the vapor pressure of bromine trifluoride has been determined. Ruff and Braida (4) measured some of the physical and chemical properties including the vapor pressure over a limited range, 4 to 136 mm. The present investigation extends the vapor pressure data to 2 l/2 atmospheres on material of high purity.