Several operations that are important to the process as carried out in Task III (Reduction) are performed by the mixer. In order to specify the process certain tests were made to study these operations and are discussed in this report. They include: Mixing Time, Mixer Discharge Rate, Mixer Holdup, and Mixer Capacity. A description of the test, conclusions and recommendations is provided.

The essential structural element which differentiates metal chelate compounds from metal coordination compounds, or metal complexes in general, is the existence of some linkage between two or more of the donor atoms in the first coordination sphere of the metal. It is the purpose of the present discussion to examine the influences that this structural factor may have upon the physical and chemical properties of chelate compounds. Examples of well known, simple coordination compounds involving a variety of donor atoms (Oxygen, nitrogen), as well as a variety of electrostatic situations are shown in the following formula. Below each one are listed a few corresponding chelate structures.

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The Reactor Safeguard Committee formula for the allowable minimum distance between a reactor and the public domain is expressed as: r = 0.01{radical}P, where r = radius from reactor in miles, and P = reactor power level in kilowatts. The six plates in this report illustrates the application of this formula for Hanford Works, both for individual reactors and all reactors in an area.

This progress report from the Argonne National Laboratory covers the work in Biological and Medical Research, Radiological Physics, and Health services for the quarterly period ending March 31, 1952. Numerous experiments were conducted in an attempt to answer some of the questions arising from exposure to ionizing radiation, especially X radiation. Some of the research involved the radiosensitivity of cells and some involved animals. The effects of radium in humans was also evaluated. Other studies were performed in biology, such as the effect of photoperiodism on plant growth and the biological of beryllium.

This report addresses the biological effects of ionized radiation

This test project is being carried on for the purpose of testing certain machines which are designed to charge and discharge reactor units with process metal while the unit is in operation. Satisfactory charging of process pieces while the reactor now required for charging operations. These presently required shutdowns are costly in terms of production time, and may cause undesirable thermal stresses in the unit as it changes power level. If charging can be accomplished during operation, reactor shutdowns would only be necessary for maintenance or emergency purposes. During the testing of these metal handling machines, problems have arisen involving the behavior of the process pieces as they are charged. Because these problems directly affect the charging operations, they are being closely investigated also. the machines covered by this report are designated as pressurized machines since they contain the same water pressure as the end of the process tube on ;which they are located. In most of the test work covered by this report, the full scale pressurized charging machine was replaced with a small charging cylinder. The charging operation was simplified by this change.

Final approval of a flow-pressure characteristic curve and orifice pattern for C Pile is desired as soon as possible to allow the completion of orifice assemblies and parallit instrumentation. The presentation of a recommended flow-pressure curve and an orifice pattern has been delayed by a lack of experimental flow data on the C Pile flow system. Discussion with members of the C-431-B working committee and Pile Technology Unit personnel indicated that the use of flows higher than those recommended by the Reactor Unit, in HDC-2327, was desirable on the basis that the costs of supplying more water to C Pile than required by present outlet temperature limits will be small compared to the probable saving that can be made in reduction of corrosion and slug rupture frequency. Using this agreement as well as previous data and the assumption of low enrichment as a basis, a preliminary recommendation of a higher flow curve is presented.

The over-all objectives of this project encompassed testing the suitability of standard and special laundering methods and standard equipment for field decontamination of clothing; evaluating the contaminability and decontaminability of selected fabrics, and testing of experimental clothing monitoring instruments. Garments and fabrics contaminated by controlled methods were used during the operation for testing the equipment and evaluating fabrics and formulae. 8tandard Army laundering methods and equipment, including wooden washers, were effective for decontaminating clothing in the field. A decontaminating laundry formula employing citric acid and tartaric acid followed by either an organic or inorganic chelating agent results in a higher degree of decontamination than other formulae tested. The standard Quartermaster Corps mobile field laundry formula resulted in satisfactory decontamination with the type of soil and activity encountered and the cost of supplies is approximately one-tenth as much as the special formulae. Woolen garments and fabric swatches were decontanninated by laundering as readily as cotton or synthetic fabrics. Clothing monitoring instruments under development appear suitable for monitoring clothing under field conditions to determine the degree of contamination both before and after precessing. (auth)

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A high-density concrete shield is proposed for the biological shield. Adequate shielding of personnel and equipment can be obtained for about two-fifths the cost of a laminated shield of steel and masonite. The proposed shield is expected to behave satisfactorily during the life of the Reactor Unit and, in addition, the shield will possess considerable resistance to earthquake and blast loads. Details of design specification are given.

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This document is a compilation of obsolete security codes, convenience codes and local jargon in use, or previously used, at Hanford Works. It is compiled to aid readers in understanding the Hanford report literature, particularly that originated in the early years of the Project.

This is a progress report of the production reactors on the Hanford Reservation for the month of April 1952. 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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Discussed activities include: boiling consideration studies, C pile Panellit ranges and orifice sizes, testing of time delay relay, tube water flow studies, extrapolation of pile design data, temperature distributions in cold-sized canned J-slugs, pressure drop film studies, short tube mockup, film formation studies experiment, pile pressure drop increase studies, pile process specifications, loss of pile cooling water study, thermocouple slug, measurement of slug bond coefficients, slug temperature distribution, resistance heating of slugs, induction heating of slugs, shield temperatures with no water flow in the thermal shield cooling pipes, distortion and stress in the biological shields of B, D, and F piles, and studies of high density concrete for biological shields.

Eleven thorium-carbon alloys in the range 0.02 to 2.0% carbon were prepared by vacuum-arc melting. The hardness varied from 19 R/sub A/ for the 0.02% alloy to 108 R/sub B/ for the 2.0% alloy. The preparation of thorium- chromium alloy was hampered by a reaction with the zirconia molds, which results in porosity in the casting. The failure of aluminum-silicon bonded X-10 slugs after heat treatment for seven days at 400 deg C was traced to the failure to remove tin after the tin dip and the presence of a gas during heat treatment. Tensile tests were made on extruded thorium, and no correlation was found with extrusion variables. A composition effect was found, however, which showed a linear relationship between carbon content and tensile strength. Creep tests on thorium, uranium, and Inconel continue. The program of evaluating the variables in the fabrication of clad fuel elements, using MTR techniques was concerned mainly with the distribution of UO/sub 2/ in the core compact, the temperature of rolling, and the particle size of the metallic core powder. Progress is being made in the preparation of three-layer laminates without the use of a protective can during the hot-rolling operation but with the …

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Estimated water flow rates at H Pile for various postulated conditions are given. The conditions under which the data are valid are as follows: (1) the estimated accuracy of the tube flow rates is {+-}5%, and of pile flow rates {+-}7%; (2) the pile flow rates are based upon the present tube geometry, orifice zone pattern and total flow at H Pile; (3) the flow rates should be increased about 2% if film-free slugs and tubes are considered; and (4) flow rates for enlarged fittings are based upon fittings similar in shape to the present H Pile fittings. The maximum tube flow rates for the DR Pile would be about 2% greater than those given in the table for present tube fittings. For enlarged fittings, the rates for DR Pile tube would be the same as those given for H Pile tubes. The ultimate permissible flow will depend, in part, upon limitations on maximum cross-header pressure and maximum tube inlet pressure, and upon the instrumentation necessary to detect abnormal tube flow conditions.

Attention is now being drawn to the refractory properties of the pure dioxide of uranium, which make it suitable for special applications, such as the melting of pure uranium. Properties of uranium dioxide are described as they relate to fabrication. Forming of UO{sub 2} refractories by pressing and slip casting is discussed, as well as the firing of urania refractories and the properties of fired ware. Health hazards pertaining to UO{sub 2} are briefly described.

Since 1945 the routine production of plutonium (``A`` buttons) at Atomic Energy plants has been accomplished by heating mixtures of plutonium tetrafluoride, calcium and iodine in crucible-bomb assemblies. Yields above 97% and metal of adequate purity are consistently obtained by this process. Plutonium (``X`` button) production has also been carried out routinely by including plutonium turnings with the powder mixture given above. A majority (several thousand) of buttons produced in the 234-5 Building have been ``X`` buttons made by recycling up to 1.1 units of turnings/unit of plutonium in the plutonium tetrafluoride. Operating hazards exist in either process, however, and these are reviewed below.

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