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The Fermi-Thomas model has been used to derive the equation of state of matter at high pressures and at various temperatures. Calculations have been carried out both without and with the exchange terms. Discussion of similarity transformations lead to the virial theorem and to correlation of solutions for different Z-values.

This report details events of importance reported by the Hanford Operations Office for the week ending April 27, 1949.

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The mean heat capacity of a sample of powdered U/sub 3/O/sub 8/ was determined as a function of temperature from measurements of heat content. A thin-walled nickel capsule containing the material was heated in an electric furnace and dropped into a water calorimeter The Mean heat capacity values calculated from the experimental data were nearly constant over the temperature range, room temperture to 250-975 deg C (482-1790 deg F). The average value was 0.074 plus or minus 0.004 cal gm/sup -1EDE/C/sup -2/ (0.074 plus or minus 0.004 Btu lb/sup -1 deg F/du p -1/). From 975-1100 deg C (1790-2012 deg F) a small rise was observed. (auth)

This report details events of importance reported by the Hanford Operations Office for the week ending April 20, 1949.

The objectives in producing neutron sources are to produce uniform products of as high efficiencies as possible from the neutron yielding elements and to do this in the safest manner. The purpose of the present work was to improve the methods of preparing sources and at the same time increase the types of sources available. Lithium, sodium, and their compounds were chosen because the neutron fluxes and energies are low, thus making the experimental work less hazardous to the operator. Also, the elements are quite reactive, so that techniques which are successful with them can be easily adapted to other materials. Solvents for polonium, ways of mixing polonium and target, neutron yields, reproducibility, decay of the sources, means of recovering polonium, and materials for containers, were investigated.

The mean heat capacity of a sample of powdered beryllium carbide, a possible moderator material for a nuclear reactor, was determined as a function of temperature. A thin-walled stainless steel capsule containing the material was heated in an electric furnace and dropped into a water calorimeter. The following linear equation for mean heat capacity over the temperature range 50 f C-T f C as a function of temperature, T, was derived from the data by the method of least squares: C/sub p/ = 0.299 + 2.16 x 10/sup -4/ T f C el temperatures 0.005 cal gm/sup -1/( f C)/sup -1/. The numerical value of C/sub p/ expressed by this equation is also equal to the mean heat capacity in Btu lb/sup -1/( f F)/sup -1/. (auth)

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This is a progress report of the production reactors on the Hanford Reservation for the month of March 1949. This report takes each division (e.g. manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month. (MB)

The experiment outlined in this proposal has the possibility of giving an answer to the important question, 'Does the neutrino exist'? It is unfortunate that at the present time, there is no convincing experimental that neutrinos exist. Two recent articles review the status of various experiments which could give information about neutrinos. In general, these experiments give results in agreement with the predictions of beta decay theory. But actually, if even the most complete of the 'recoil type' experiments could be performed satisfactorily, all that could be concluded would be the following: the energy and momentum relationships in beta decay are consistent with the theory that the known energy deficit is carried away by a single particle. But to emphasize the fact that this would not constitute a proof of the real existence of that particle, the following quotations from the review articles should be noted. Crane says, 'All of the evidence about the neutrino is, as already pointed out, indirect in character since neutrinos have not yet been caught after leaving the nucleus. It can, of course, be argued on very general grounds that, if energy is not conserved between nucleus and electron, momentum should not be expected to …

This report details events of importance reported by the Hanford Operations Office for the week ending April 13, 1949.

Equipment was developed for the continuous burning and leaching of ground carbon in order to recover uranium for the proposed Closed Cycle Beta Process. The burning apparatus consisted of a vertical tube with a grate to support the carbon. An uppdraft of air was used to support combustion. The burning rate of the apparatus was 500 grams of carbon per hour; combustion averaged over 98% complete. The leacher consisted of a heated nitric acid bath divided in four compartments through which ground carbon was pushed by rotating paddles. The acid flowed, by gravity, countercurrent to the carbon.

This progress report discusses activities at P Division for the month of March, 1949. All piles operated at 275 megawatts throughout the month except for the outages listed under Area Activities in this report. The average time operating efficiency''was 91.4%. A total of 47 tons of metal was discharged from the piles during the month. During the month, 16.6 tons of alpha-rolled, triple-dipped metal were discharged without difficulty at a nominal concentration of 320 megawatts day (MWD) per ton. Inspection of selected tubes of this material indicated that exposures at this level are satisfactory. In view of these results the programs of stepwise increases in concentration will be continued, with the next test tonnages being discharged at a nominal concentration of 360 MWD per ton. The nominal monthly production rate of acceptable canned pieces was reduced from 90 tons to 60 tons on March 28. This curtailment of production was possible in view of the favorable inventory of slugs available for charging DR and H piles.

Due to a forecasted increase in pile area production as well as a possible decrease in batch size of the separations process, an increase in the capacities of the separations plants is indicated. It is the purpose of this report to review this relationship in the light of existing data and to determine how this additional capacity can best be attained through the use of either the proposed semiparallel or complete parallel methods of operation. Emphasis will necessarily be given to consideration of cost, timing, use of minimum buildings and equipment, and the obtaining of optimum production time cycles.

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This report discusses recommendations for development work on the Redox Production Plant. It contains an outline for a relationship procedure between the architect engineer and General Electric Design Division; preparation of a material balance and process flow; the preparation of engineering flow diagrams, including lists of standard symbols for these diagrams; a material and equipment list; a project cost estimate; and Procedures covering institution and execution of work involving studies by the Design and Construction Division.

This report details events of importance reported by the Hanford Operations Office for the week ending April 6, 1949.

Minutes of conferences held at Chalk River, Ontario. The subjects discussed related primarily to separations processes.

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The notes and recommendations contained in this report relate to the design and construction of the Redox Production Plant with its associated Tank Farm at Hanford. All current development work for the Redox Program was to be transferred to the Redox Production Plant. [The Redox plant used a reduction-oxidation process for fuel separation that allowed recovery of uranium as well as plutonium for the first time. It succeeded earlier plants (T and B) that used methods based on the bismuth phosphate process that recovered only plutonium.]

The study was made in an effort to determine experimentally the relationship between Logac 1,2 counts and the thickness of the slide on which a sample is mounted.

The constant temperature bath is in operation. A ballistic type instability was detected in the calorimeter circuits and corrected by grounding the bath. Calorimeters 37, 39, 40, and 43 have been installed are now being run. Calorimeter 40 was found to be unstable, and is to be disassembled and examined for the trouble. Calorimeter 46 was finished and placed in operation. Construction details are discussed. Six Logac samples were run in Calorimeter 38. Tests of this calorimeter are in Table 1. Comparison of Calorimeter 38 in a water bath and in an ice bath is shown in Table 2. Good results were obtained for such a drastic change in environment. Calorimeter 38 was turned over to Calorimetric Assay marking the end of the tests of this particular microcalorimeter. Calorimeter 44 was completed and installed in the ice bath. Table 4 shows the results of tests. The zero bridge potential is small and is very stable compared to Calorimeter 38. The comparison of the values with those from Calorimetric Assay is summarized in Table 3. The characteristics of Calorimeter 44 are shown in Table 5. Construction details are given for the platinum-manganin bridge-type thermometer. An instrument was needed that could be …

This report details events of importance reported by the Hanford Operations Office for the week ending March 30, 1949.