Report containing articles, manuscripts, and tabulations of recorded spectra created by the Spectroscopic Laboratory of the University of Chicago.

Instead of solving the nonlinear differential equation which governs the compressible flow, an approximate method of solution by means of the variational method is used. The general problem of steady irrotational flow past an arbitrary body is formulated. Two examples were carried out, namely, the flow past a circular cylinder and the flow past a thin curved surface. The variational method yields results of velocity and pressure distributions which compare excellently with those found by existing methods. These results indicate that the variational method will yield good approximate solution for flow past both thick and thin bodies at both high and low Mach numbers.

Report containing articles, manuscripts, and tabulations of recorded spectra created by the Spectroscopic Laboratory of the University of Chicago.

From purpose of report: The primary purpose of this report and its appendices is to transmit to the AEC the principal results of the experimental and engineering work done on the low-temperature process and to describe the factors which led to the designs finally adopted.

This report discusses the production of large-diameter zirconium crystal bars in a 16 inch diameter, Hastelloy B, de Boer unit in order to increase production efficiency.

Abstract: Summaries of the geology and mineral deposits, and appraisals of the uranium possibilities of the various regions of Alaska are presented in this report.

Technical report outlining the determination of the effective resonance integral for U238 as a function of the mass ratio for cylinders of 5/8" to 3" diameter. Also gives a linear approximation of the effective resonance integral with infinite shielding in the form of a function. [From Abstract]

Technical report presenting a summary of the flowsheets, equipment, and progress for the Oak Ridge National Laboratory (ORNL) pilot plant development of the Purex Process and of the ORNL Metal Recovery Program. As of this report, conversion of the Purex pilot plant equipment in Buildings 3019 and 3503 is 90% complete. The building structure for the ORNL Waste Metal Recovery plant had been completed, and 15% of the process equipment had been installed. The first hot runs for this plant were scheduled for June, 1951. [From Abstract; Introduction]

Technical report outlining how uranium hexaflouride was prepared be the direct combination of irradiated uranium metal with elemental fluorine and subsequently decontaminated by adsorption, filtration, and sublimation on a laboratory scale. Report proposes a survey of other methods of preparing UF6 from uranium metal, a study of adsorption techniques for removing plutonium from UF6, and an investigation of fractional distillation for removing the volatile fission product fluorides from UF6. [From Abstract, Summary]

The 100-C project is to be located adjacent to the present 100-P Area. It is planned to build an addition to the present 181-B River Pump House using the same elevations for pump settings, intakes, and floors as for the present pump house, thus maintaining the same suction conditions and flood protection as B Area. The 105 Building will be located on higher ground than B Area and, therefore, protection against possible flood damage is assured.

The 100-C project is to be located adjacent to the present 100-B Area. It is planned to build an addition to the present 181-B river pump house using the same elevations for pump settings, intakes, and floors as for the present pump house, thus maintaining the same suction conditions and flood protection as B Area. The 105 Building will be located on higher ground than B Area and therefore, protection against possible flood damage is assured. This report is divided into the following sections: (1) general description of project; (2) addition to existing river pump house; (3) raw water lines from 181-B addition to 183-C lead house; (4) the 183-C filter plant; (5) 190-C process pump house; (6) power house addition; (7) high tanks; (8) retention basins; (9) outside streamlines; (10) primary substation; (11) outside underground lines; (12) outside electric lines; (13) roads, railroads, walks, fences; (14) structural design of all buildings; and (15) architectural design of all buildings.

Authorization has been received in the form of Modification No. 5 to Directive HW-158, dated March 23, 1951 to provide the necessary equipment and piping in the currently planned UO{sub 3} plant to permit the segregation of UO{sub 3} arising from the processing of stored metal waste (TBP) from that arising from ``current`` pile operation (Redox). In anticipation of this, the S Division, Manufacturing Divisions, requested that a study be made of the feasibility and cost of providing facilities for such segregation. This report is the result of that study. It concludes that by providing additional liquid storage and handling equipment, the desired segregation can be accomplished at a cost estimated to be approximately $128,000. $106,500 would be for Construction and $21,500 for Engineering. The schedule for this work will be reflected in the forthcoming modification to the C-361 Project Proposal. The general method of operation is alternately to store and process solution from TBP and Redox. The solution from TEP will be of a composition equivalent to the formula UNH and will require five days each week to process in the decomposition pots. The solution from Redox is received as 60% UNH and is batch concentrated in the storage …

This is a progress report of the production on the Hanford Reservation for the month of February 1951. 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.

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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.

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 question of the conditions under which living matter originated on the surface of the earth is still a subject limited largely to speculation. The speculation has a greater chance of approaching the truth insofar as it includes and is based upon the ever wider variety of established scientific fact. One of the purposes of the herein reported observation was to add another fact to the ever increasing information which might have any bearing upon this most interesting question. It is not our purpose in the present communication to discuss the various proposals or the arguments which have been adduced for and against them. One of the most popular current conceptions is that life originated in an organic milieu on the surface of the earth, (1,2,3,4,5). The problem to which we are addressed is the origin of that organic milieu in the absence of any life. It appeared to us that one source, if not the only source, of reduced carbon compounds in complex arrangements might be the interaction of various high energy radiations with aqueous solutions of inorganic materials, particularly carbon dioxide, and nitrogenous compounds such as ammonia and nitrogen, since it appears that these compounds were the commoner …

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A tentative nickel-plutoniuni constitutional diagram was based on data obtained by thermal analysis, metallography, and x-ray-diifraction techniques. The systema is a complex one with the following important features. Nickel is soluble in epsilon plutonium, extending the epsilon field to 4.3 at.% nickel at 465 deg C. Nickel and plutonium form six intermetallic compounds, PuNi, EnNi/sub 2/, PuNi/sub 3/, PuNi/sub 4/, PuNi/sub 5/, and PuNi/sub 9/. The compound PuNi/ sub 5/ forms congruently from the melt at approximately l300 deg C, whereas the other compounds forma peritecticaliy. The extended epsilon field termainates in a eutectoid reactlon at 415 deg C and l.5 at.% nickel. Epsilon plutonium and the compound PuNi form a eutectic system at 465 deg C with a eutectic compcsition of l2.5 at,% nickel. Nickel and the compound PuNi/sub 9/ form a eutectic system at l2l0 deg C with a eutectic composition of 92 at.% nickel. Plutonium forms a limited solid solution with nickel. (auth)

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