This is the seventeenth quarterly report on our echelle project, as numbered above. Our work this quarter has to some extent been directed towards the Spectroscopy Symposium held at Argonne National Laboratory on February 15, 16, and 17. This report consists principally of brief abstracts of the two papers given at this meeting. Progress since the last quarterly report included completion of the echelle comparator calibration, and the successful production and photographing of the desired spectra of praseodymium and erbium in strong magnetic fields. Considerable interest was aroused by these papers, not only because rare earth spectra are being analyzed, but because of the general applicability of our experimental techniques in producing the spectra.

Monthly magazine discussing natural resources, parks, hunting and fishing, and other information related to the outdoors in Texas.

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.

Monthly journal about library issues in Texas including collection development, programming and activities, managements, and other topics of interest.

A new method to procure RaLa sources was proposed by Group CMR-10, Los Alamos Scientific Laboratory. This method depended upon irradiation of small-diameter U235 wire in the Materials Testing Reactor, Arco, Idaho. A procedure for cladding and sealing U235 wire in stainless steel tubing, by drawing, plugging the tube ends, and welding, was developed, tested, and proved to be satisfactory.

The hydrogen evolution method for the determination of uranium trifluoride which was developed by Manning, Miller and Rowan has been used for the determination of trivalent uranium in this laboratory for the past three years. The method has been applied to many different sample types supposedly pure UF3, mixtures of UF3 and UF4 and the large variety of mixtures of fluoride salts that have been investigated as possible nuclear fuels. These mixtures contained alkali metal, beryllium and zirconium fluorides. Several modifications have been made that have substantially improved the performance and ease of operation of the method. These improvements include the use of (1) an inexpensive, long-lasting source of pure carbon dioxide, (2) vacuum to assist in purging the system of gases that are insoluble in potassium hydroxide solution, (3) deaerated acid that has an extremely low quantity of non-absorbable gases, (4) slower flow rates of purging gas, (5) a sampling technique to minimize contamination, and (6) more dilute absorber solution to reduce film error. It is the purpose of this report to show the effect of these modifications and the applicability of the method various sample types that contain uranium trifluoride.

Observations of the effects of neutron damage to zirconium oxides led to the conclusion that the cubic form of ZrO2 is more stable to such damage than the monoclinic form. It has been reported that zirconium corrodes more rapidly in certain liquids when exposure is made under radiation (neutrons and fission products). It is well known that on heating monoclinic ZrO2 a transformation, monoclinic to tetragonal (very similar to cubic), occurs at about 1500°C. The transformation involves sufficient atomic rearrangement that pieces of ZrO2 normally crack and crumble. It is suggested that the effects of neutrons on monoclinic ZrO2 may be similar so that a protective oxide film on the metal would be destroyed soon after its formation. It might be possible, therefore, that the protective oxide film on zirconium metal which is normally monoclinic might be less resistant to corrosion under radiation damage than a similar film which was cubic.

Consideration has been given to various forms of fissionable material for use in atomic reactors, including the pure metals, their alloys and compounds. Of particular interest is the dioxide of uranium which is refractory and corrosion resistant in some environments.The oxide is useful in both granular and bulk forms. Small grains of uranium oxide can be mixed with other materials to form matrix type elements where they serve either as a convenient or necessary form of fuel or fertile material. For other applications the oxide may be fabricated in bulk form such as pellets, rods, plates, or blocks.There is a need for knowledge of the properties of the properties of this oxide, particularly as it affects fabrication in the various forms required. This knowledge is also required by reactor designers and engineers. There is in addition a challenging field for basic studies of sintering rates, oxidation behavior and other phenomena. Fabrication techniques have been developed to produce uranium oxide in various forms with consideration given to the economy of production. The continued application of basic knowledge of these materials has led to simpler. more practical means of fabrication and has thus widened the scope of their use in atomic reactors.

The countercurrent gas-liquid system BF3(g)—anisole·BF3(l) for the concentration of boron isotopes has been studied. The single-storage separation factor varies from 1.039 at 0°C to 1.029 at 30°C. Rate of exchange is rapid, and, with efficient contacting equipment, complete exchange may be obtained in less than 15 sec. A total separation of 1.525 has been realized in laboratory equipment. The critical-product reflux reaction is quite efficient. Only about 55 moles of BF3 remain in each million moles of effluent solvent under laboratory conditions. The vapor pressure of BF3 over the complex rises sharply as the temperature is increased. At 0°C the pressure is 150 mm Hg, and at 40°C the pressure has risen to 1800 mm Hg. From vapor-pressure measurements, an approximate upper limit of ΔH= -12kcal per mole of complex was calculated for the reaction [equation not transcribed]. Qualitative tests indicate good resistance of anisole to decomposition by BF3 under plant conditions. The uncatalyzed exchange of boron between BF3 and BCl3 was found to be too slow to be exploited in a countercurrent system. The single-stage, equilibrium separation factor for the Nitrox system is a function of acid concentration. At 26°C the factor ranges from 1.064 with 1 M acid …

The enthalpies and heat capacities of seventeen fluoride mixtures in the liquid state have been determined using Bunsen Ice Calorimeters and copper block calorimeters. The fluoride mixtures were composed of the fluorides of two or more of the following metals: lithium, sodium, potassium, beryllium, zirconium, and uranium. The enthalpies and heat capacities of most of these mixtures were studied in the solid state also. Estimates of the heat of fusion have been made. General empirical equations have been developed which represent the enthalpies and heat capacities of the fluoride mixtures in the liquid and in the solid state.

Calculated data and graphs describing the effects of continuous thermal-neutron irradiation of thorium, the usual method of operations of homogeneous reactors, are presented.The buildup and decay of U^233, Pa^233, other heavy isotopes, and fission products are considered on the basis of best available cross-section and fission-yield data. The effects of the heavy isotopes and fission products on neutron economy are discussed.

A preliminary soil column experiment with a waste sample from the 207-S-11 well, which monitors the 216-S cribs, indicated that cesium was absorbed almost completely by the soil but that strontium breakthrough to ground water in the near future seemed likely. Accordingly, it was suggested that the 216-S wastes be discharged to a new disposal site, and that samples of the wastes which are currently being discharged to the 216-S cribs be obtained for soil absorption tests. The primary purpose of these tests was to obtain data which could be used to suggest ways and means of improving the absorption of strontium by soil from the process condensate stream (D-2_ and the cell drainage stream (D-1), both of which have been discharged to the 216-S cribs for the past several months.

The use of process-solution-lubricated sleeve bearings in rotating equipment is quite extensive at H.A.P.O. The difficulty or impossibility of providing contact maintenance, the poor lubricating qualities and corrosive natures of most of the process solutions, in addition to radioactivity, impose stringent restrictions on the selection of materials of construction of these bearings. Prototypical evaluation of materials indicating suitable characteristics in preliminary testing, both in the Corrosion Laboratory and in the bearing test machines, is necessary to establish behavior and compatibility under actual or simulated process conditions. These preliminary tests showed that gold and gold alloys might be used as satisfactory materials for pump bearings under certain conditions. This report presents the test results obtained while testing bearings in pumps prototypical or identical with process plant equipment.

The design criteria are written to supply information for the preparation of a project proposal covering budget item B-2265 for Fiscal Year 1956. The function of in-line instrumentation installed shall be the rapid on-the-spot analysis of process variables for quick presentation to process operators for immediate action in process control. Alarm or safety circuits may be incorporated on the equipment.

The purpose of this report is to establish a practical control limit for the activity density (concentration) of radioactive material that may be permitted in large-volume waste waters discharged from the Hanford separations plants to open ponds on the surface of the ground nearby, in consideration of the radiological hazards,

In reduction reactions of CeO₂, with calcium and a CaCl₂ flux, the use of vibrational energy was shown to have a marked effect on the yield of coalesced metal. Buttons of 40 to 50% theoretical yield were obtained from the vibrated reductions. As the flux concentration is decreased, the slag becomes more viscous containing undissolved CaO. The undissolved CaO present prevents the metal from completely coalescing, but the metal can be recovered from the slag and coalesced under CaCl₂ containing a small amount of calcium to reduce any oxide skin present. Cerium pellet yields of 50 to 60% metal were obtained by the procedure and were not difficult to handle in air. Cerium was used as a stand-in material for plutonium.

An investigation of corrosion in the 327 Building's water storage basin was made to determine whether the static storage of aluminum jacketed fuel elements could cause corrosion effects that would interfere with studies of in-pile corrosion.

The purpose of this study was to develop and design a cutting torch which would slit aluminum tubes in a graphite matrix without damaging the graphite.

The purpose of this report is to describe the tests performed on the D-12 waste evaporator, to present and evaluate the data obtained during the test, and to make recommendations for the implementation and operation of present and future installations of bayonet tube bundles.

It is the purpose of this report to: 1. Present the results of a study to estimate the range of attainable boiling conditions in the 1706 KER loop design on the bases given in reference (12). 2. Present an outline of the significant modifications and equipment changes necessary to obtain the process conditions desired.

A portable, light weight transistorized alpha, beta, and gamma survey meter was designed and fabricated.

Discussing uranium in the Sharon Springs Member of the Pierre Shale in South Dakota and Northeastern Nebraska

Discussing the investigative drilling of the Elk Ridge Area in San Juan County, Utah.

This document, dated February 1, 1956, presents the results of a study made to ascertain the most desirable method, both from an economical and operational consideration, of utilizing the acid recovered in the 224-U Building at HAPO.