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- Musical Opening Choruses, Finales and Production Numbers for Soldier Shows
- A selection of opening choruses, choral finales, sketches with comedy songs, and miniature musical comedies, mostly excerpted from pre-existing Broadway shows with lyrics adapted to Army, Navy, or Marine Corps themes. Soldiers were encouraged to incorporate these numbers into their own shows, adapting them further as needed, and to use them as inspiration for writing their own original numbers.
- Temperature Effect in Homogeneous Pile
- Some idealized considerations of the temperature field in the homogeneous pile are given. It is crudely estimated that the effective mean temperature rise of the pile to be used in calculating the k loss is something like 3/4 the rise in temperature of the slurry in passing through the pile.
- The Resonance Absorption Spectrum of Uranium
- A model for the capture spectrum of uranium is introduced in which levels occur at 7, 30, 30+D, 30+2D, ..., ev. Gamma ray and neutron widths are derived from the experimental data for values of D between 10 and 25 ev. The constants of the 7 volt level prove to be independent of D. Extrapolation, using the one level formula, gives a capture cross section at (1/40) ev of 4.9 x 10(24) cm2; this number is, however, quite sensitive to the value taken for the resonance activation. Both neutron and gamma ray widths for the higher levels are approximately proportional to D.
- Some Cases of Pile Activity Flattening
- Radial flattening of activity in the cores of spherical and cylindrical piles is discussed in connection with pile control and power improvement. Partial flattening as a result of k loss from temperature rise is also considered.
- The Contamination of Cooling Water by a P-9 Plant
- The following sources of contamination in cooling water of the P-9 plant are considered: (1) Fission recoils, (2) Corrosion of metal, (3) Recoil from aluminum, (4) Induced activity in the water. It is found that for a P-9 plant of 3.5 x 10(4) KW contamination of the river at "X" should not exceed the .1 r criterion unless coating failure occurs. Tables of the amount of coating failure permissible are given as a function of holdup time.
- The Effect of Fast Fission on k
- The importance of fast neutron fission (i.e., fission caused by neutrons before being slowed down) was recognized by Szilard, and calculations similar to the present one have already been carried out by him, Feld, Ashkin, Wheeler, Wigner and others. The purpose of the present paper is to give a general formula for the contribution of fast fission to the multiplication constant, which will include all the cases already considered and will be applicable to more complicated geometries than those considered by the previous writers.
- On the Multiplication Constant of Homogeneous Mixtures of U with Various Moderators
- The following represents a summary of calculations on the multiplication constant of homogeneous mixtures of uranium and different moderators. These calculations were made possible by Fermi's determination of the age of neutrons and by the extrapolation to higher scattering cross-sections of the resonance absorption of uranium as measured by C. Creutz. According to Fermi, the former quantity is 120 sq. cm. The latter is given in the two attached graphs. The first (Fig.1) of these goes as high as a scattering cross-section of 70 x 10-24 cm.2 per uranium atom, and its highest point is taken from a measurement of Cruetz's in which a mixture of U3O8 and graphite was used.
- Effect of Temperature on the Resonance Absorption of Neutrons by Uranium
- The resonance absorption of uranium for neutrons has been investigated between 20 degree C and 1000 degree C. Experiments were caried out on both UO2, density 4.63, and metal. The resonance activity was measured with respect to that of an iodine monitor at several different temperatures and the ratio of activity at temperature T to that at 20 degree C was determined. The increase in activity is 0.9 per cent per 100 degree C for the oxide and 1.1 percent per 100 degree C for the metal. The period of U239 was found to be 23.54 +- 0.05 min.
- Radioactivity of the Cooling Water
- The most important source of radioactivity at the exit manifold of the pile will be due to O19, formed by neutron absorption of O18. A recent measurement of Fermi and Weil permits to estimate that it will be safe to stay about 80 minutes daily close to the exit manifolds without any shield. Estimates are given for the radioactivities from other sources -- both in the neighborhood and farther away from the pile.
- Temperature Coefficient of the Reproduction Factor for Different Lattice Arrangements
- The temperature coefficient is calculated for various lattice arrangements, taking into account the variation of [formula], suggested by Fermi. Four contributions are included: leakage, levelling of the dip in thermal neutron density in the lump, resonance absorption, and hardening of the neutrons as they penetrate a metal lump. The departure of neutron temperature from lattice temperature decreases the total coefficient. Values are given for 3 typical piles; in general, the larger the uranium elements, the less stable the pile. A rod lattice tends to be more stable. A pile with metal lumps over 50 lbs. will be unstable.
- Effective Temperature of Neutrons in a Lattice
- The average energies of neutrons emitted from a graphite column at 22 degrees C were compared by measurement of the cross section of boron for neutrons which are stopped by cadmium. At a distance from the neutron source great enough to insure that the neutrons were in thermal equilibrium the average energies of the emerging neutrons were found to be proportional to the temperature within the limits of the experimental error. A measurement made with boron absorbers which had been thus standardized in the graphite column indicated neutrons emerging from the chain reacting pile to have an average temperature approximate 60 +- 50 degrees above that of thermal neutrons emerging from the graphite column at 22 degrees C. Such a measurement made inside the chain reacting pile indicated the average temperature of neutrons therein to be about 65 degrees +- 15 degrees above the average temperature of neutrons in the graphite column.
- Low-Density UO2 Pile
- The multiplication factor and minimum pile size for a multiplying pile using UO2 powder of density 1 have been computed. It appears that a k of 1.0177 is possible for a volume ration of V/V001=3.33.
- Chain Reaction of Pure Fissionable Materials in Solution
- The critical mass of 94-239 and the corresponding critical dimensions of homogeneous mixtures of 94-239 with various moderating media been calculated as a function of the concentration of 94. A simple transformation makes the figures applicated to92-235. the results are in essential agreement with the preliminary estimated made independently by Oppenheimer and Serber. The problem of the stability of a chain reaction in solution and questions of protection are discussed.
- Studies on the Determination of Carbon by the Low Pressure Combustion Method
- 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.
- Metallurgical Laboratory, Chemical Research - Analytical, Graphite Purity Research Program
- Abstract. Chemical analytical studies of graphite raw materials have revealed new sources of petroleum cokes and pitches of greater purity than those previously used in the manufacture of project graphite. The use of these raw materials of exceptional purity has resulted in an improvement in k of the order of one per cent as compared with the AGOT-AGNT graphite typical of the previous production. A study of the graphitizing process has shown that no dangerous impurities are introduced in the graphite in manufacture; rather, the process actually purifies. furthermore, impurities are distributed homogeneously within the furnace charge; thus the AGOT-AGNT distinction is no longer necessary. A comparison of the methods of graphite testing has demonstrated excellent correlations between chemical analytical data, the results of the function test at Argonne, and the sigma pile experiments. It may therefore be inferred that chemical testing should be an adequate control of the graphite purity. Methods are described for the analysis of ash, B, V, TI, FE, and Ca in petroleum coke, pitch, and graphite.
- Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Errara for CC-918
- Technical report listing the errata for pages 2, 4, 5, 6, 7, and 8 for report CC-918.
- Chemical Research -- U233 Production and Extraction; Report for the Month Ending June 21, 1943
- 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.
- Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending May 15, 1943
- 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.
- Report on Trachyte district, Henry Mountains area, Garfield and Wayne Counties, Utah
- A report regarding the Trachyte District, located in the Henry Mountains Area, Garfield and Wayne Counties, Utah.
- Summary of an investigation of vanadium and uranium occurrence in Huerfano Park district, Raton Basin area, Huerfano and Costilla counties, Colorado
- A report on the SOM-vanadium occurrences of the Huerfano Park District.
- Report on the Coyote area district, Dolores Plateau area, Colorado
- Report and corollary maps on the Coyote Mesa District, Dolores Plateau Area, Colorado
- Memorandum regarding vanadium ore production in the Colorado and Utah vanadium producing region
- Memorandum discussing the production of Vanadium Ore in the Colorado and Utah Vanadium producing Region.
- Viscosities and Densities of Fluorolube Oils
- Abstract: Since the viscosity-temperature relationships of fluorocarbons are somewhat unusual, when compared to hydrocarbons, for example, it was decided to measure the viscosities, at several temperatures, of various fluorolube oils. The calculation of the viscosity of a blend of oils is at best an uncertain operation, varying considerably with the method used. A comparison of various methods was indicated, in order that reasonably accurate values might be assumed for theoretical composites. The densities were measured at corresponding temperatures for use in converting viscosities, and for their value, per se.
- Report No. EC-2, Dated from March 24, 1943 to November 5, 1943, Contained in the Engineer's Log Book
- This technical report consists of day by day experimental data reported in Engineer's Log book, Electro-Chemistry Department, supporting Report No. EC-11 dated November 15, 1944, by W. L. Grube, Research Laboratories Division, General Motors Corporation.
- Capture Cross Section of Pb208 for C Neutrons
- From abstract: "Using the method of induced radioactivity, the capture cross section of Pb[^]208 for C neutrons is found to be .00045 ± .00015 x 10[^]-24 cm[^]2. This is definitely lower than the value of .001 x 10[^]-24 reported by Maurer and Ramm."
- Report on Methods of Preparation of Inorganic Fluorides
- From abstract: "Frequently it has been desirable to prepare pure anhydrous metal fluorides. Several general methods have proved satisfactory depending on the type of fluoride to be prepared."
- Physical Properties of Uranyl Sulfate Solutions
- Abstract: Measurements are reported of the solubility of uranyl sulfate in water at several temperatures, of the density of uranyl sulfate solutions as a function of concentration, of the variation of density of uranyl sulfate solutions of three different concentrations over a temperature range from 0[degree]C. to about 93[degree]C., and of the pH of uranyl sulfate solutions as a function of concentration as well as of temperature. The pH measurements were taken on uranyl sulfate samples prepared in several different ways and some conclusions are drawn as to the purity of theses samples.
- A Colorimetric Method
- From abstract: "This paper gives a method for determining Uranium using sodium cresotate as a colorimetric reagent. A precision is obtained of better than 2%. In carrying out analyses for Uranium in corrosion products by existing methods such as ignition to the oxide, silver reductor, or titration with ceric sulfate, it became apparent that a rapid, fairly accurate method for determining uranyl ion would be of great value. Such a method is described in this paper. The most logical color to use is that given by the ferrocyanide complex, but upon studying this, it proved to be unsatisfactory. Sodium salycilate also gives a color which has been used with some success, but its color appears to fade and is not very sensitive. A similar compound, sodium cresotate, was found to give an orange-red color and is the reagent used in the method to be described."
- Oscilloscope Camera Self Supporting
- The following report is a collection of drawings depicting the general structure of the Los Alamos oscilloscope cameras.
- Circumventing chloride ion trouble Columbia River water
- This report contains data acquired during sampling of the Columbia River water on March 26, 1945. Topics of discussion include; the elevation of chlorine levels from 4 ppm to 20 ppm, what steps should be taken to remediate the problem, and the various processes that were taken into consideration for the clean up of this chlorine. Separation processes considered include; ion exchange, distillation, precipitation, heat exchange, and recirculation through a cooling tower.
- Technical Division weekly progress report for period ending Jun 26, 1943
- No Description Available.
- [Technical progress report for Hanford 100 and 300 areas]. Progress report ending May 15, 1943
- This weekly report details technical activities for the week ending May 15, 1943.
- Technical Division weekly progress report for period ending May 29, 1943
- This report details Technical Division activities for the week ending May 29, 1943.
- Water analyses: Project 9536
- No Description Available.
- Hanford Engineer Works Project 9536: C.M.X., Bldg. 145 weekly report, November 28, 1943--December 4, 1943
- This report details activities of Hanford Engineer Works on Project 9536 during the week ending December, 1943. Tests are described which were run to determine means of eliminating the film which has been forming on tubes and slugs and causing excessive pressure drops.
- Water Analysis
- Data acquired from sampling the Columbia River water September 1, 1943, is presented. The waster was analyzed for turbidity, ph value, chemical composition, and suspended matter.
- Technical Division weekly progress report for period ending June 5, 1943
- This report details Technical Division activities for the week ending June 5, 1943.
- Weekly report CMX, Building 145
- No Description Available.
- Technical Division weekly progress report for period ending May 22, 1943
- This report details Technical Division activities for the week ending May 22, 1943.
- Site ``W`` description
- This site description of the Hanford Reservation from February 1943 gives size, topography, geology, population, water supply, railroad, highway, power, meteorological, and valuation information. Maps are included.
- Quality of Columbia River water
- This report is a memorandum sent on January 27, 1943 concerning the quality of the water of Columbia River. Topics included: ph value, water temperatures, hardness, and dissolved carbon dioxide contents.
- Weekly progress report -- Technical Section for period ending June 12, 1943
- Progress was reported from the 300, 100, and 200 Areas. It covered the X pile, aluminium corrosion, graphite purity, fuel element fabrication, bismuth phosphate extraction and decontamination processes, waste disposal from bismuth phosphate processing, control rod systems for Site W, shielding problems at the Site W separation plant, fuel element failure detection, power distribution in the Clinton pile, reactor instrumentation for Site W.
- Project 9536 - HEW - 300 Area: Metals turnings fire hazard
- This report discusses the use of coal tar to extinguish potential magnesium fires in stored metal turnings at the Hanford Engineer Works. The report is dated August 11, 1943. (JL)
- H.E.W. - 300 Area - Metal turnings - Fire hazard
- This memorandum discusses means to extinguish magnesium fires in metal turnings at the Hanford Engineer Works 300 Area. The storage of metal turnings in 55 gallon drums presented a fire hazard, for which an effective means for extinguishing the fire had not been presented. This memorandum is dated July 1943. (JL)
- Project 9336: Hanford-retention basin and effluent dilution
- This report discusses effluent dilution of a retention basin at the Hanford Works in 1943. (JL)
- Retention basins---Building 107, 100 Areas
- No Description Available.
- Measurement of the Slow Neutron Absorption Cross Section of Some Heavy Isotopes
- The following report investigates cross sections for the absorption of slow neutrons of heavy isotopes. The purpose of these measurements was to determine the cross section of an isotope of element 94 for the process of fission by the absorption of a slow neutron, relative to the cross section of U235 for the same process, that is, to measure R.
- Polarographic Determination of Uranium in Dust Samples
- Abstract: "Samples of dust are collected from the atmosphere with a Mine Safety Appliance Co. electrostatic precipitator and analyzed for uranium by means of a dropping mercury electrode apparatus. Two to three micrograms of uranium can be detected in a cell solution volume of 1 ml. Iron, nickel and chromium present in shop dusts do not interfere. Copper may interfere if present in excess but may be removed by a sulfide precipitation. Directions for preparation of cell solution and operation of the Polarograph are given. The polarographic method described may be used for determination of uranium in samples other than atmospheric dusts."
- Studies on the Electrolytic Reduction of Nitric Acid
- Report discussing the reduction of nitric acid that results from its use at the cathode for the electrolysis of uranyl nitrate. From introduction: "It is the purpose of this report to give the results of studies on the reduction of nitric acid of different concentrations, at different types of electrodes, and for various current densities in order to ascertain the effects of such changes."
- The Vapor Phase Hydrolysis of the Trichlorides of Lanthanum, Praseodymium, Samarium, and Americium
- The following report studies the reactions of vapor phase hydrolysis of the trichlorides of lanthanum, praseodymium, samarium, and americium with gas mixtures of HCl and H2O passing over the solid materials mounted on a cantilever-type quartz fiber microbalance. This report calculates the values of the heats and entropies of the reactions, as well as the heat formation of LaCl3, 1254.9 kcal mol-(-1) that was obtained by determining the heat of the solution of La metal in 1.5M HCl.