Considerable interest has been shown at HAPO in the development of a continuous ion exchange process for concentrating plutonium solutions. Development work has been performed on continuous ion exchange for both uranium and plutonium concentrations at the X-10 at ORNL. On a recent trip to Oak Ridge to discuss critical mass problems and experiments with Dr. A. D. Callihan of the ORNL critical mass facility, a meeting was also held with C. W. Hancher and R. Higgins of X-10 regarding continuous ion exchange operation. From this meeting, information was obtained that is helpful to work out nuclear safety aspects of such a plant for the concentration of plutonium solutions. An advance copy of "Countercurrent Ion Exchange" by T. A. Arehart, J. C. Bresee, C. W. Hancher, and S. H. Jury was obtained. This paper is to be presented at an AIChE meeting this fall. Preliminary blue prints of ORNL-3" Ion Exchange column design were also obtained. Upon my return to HAPO, a meeting was held with members of the Process Planning, Equipment Development, and Chemical Engineering Development Units of the Chemical Engineering Sub-Section (Separations Technology) to present the document and blue prints on continuous ion exchange and arrive at a …

Twelve uranium-magnesium fuel material samples have been irradiated in the MTR at the request of the Pile metallurgy Unit. These samples were 0.40 inch in diameter by 1.5 inches long and were canned in Zircalloy-2 capsules. The uranium used in these specimens was in the form of chips which packs about 50 volume percent. Six of the samples contained a matrix of pure magnesium and the other six contained an alloy matrix of magnesium - 1.4 weight percent silicon. Two specimens of each matrix material were irradiated to 1000 MWD/T and a like number to 5000 MWD/T. Bend tests were performed on the samples and on unirradiated control samples to secure a measure of the effect of radiation exposure on the physical properties of the material.

Under the general heading of Reactor Lattices are reported a new method of calculating resonance escape probabilities, results for the effective mass of a proton bound in the water molecule, and a comparison of similar techniques for calculating lattice constants developed independently by Hanford physicists and by a school of Russian physicists (as reported at the Geneva Conference). An estimate of maximum errors in f and η for thermal systems is described. Experiments and analysis thereof on the effects of neutron streaming in air channels through a moderator are reported. Buckling calculations and experimental results are given for graphite lattices employing 1.17-inch diameter natural uranium slugs and U²³⁵-Aluminum alloy slugs. An experimental measurement of the critical mass of an annular cylindrical array is described. Some measurements on, and the status of, construction of the Lattice Testing Reactor are reported. Under Instrumentation, development of a BF/sub 3/ counter suitable for operation at elevated temperatures is described. Some measurements on, and the status of, construction of the Lattice Testing Reactor are reported. Under Instrumentation, development of a BF₃ counter suitable for operation at elevated temperatures is described. A method of determining the screening parameter in the Thomas-Fermi model of the atom is …

"Formulas are given to express the general particle trajectory and the equilibrium orbit for a slightly disturbed synchrotron in terms of the amplitude and phase functions for the ideal machine. If these functions are known, orbit computations can be carried out by simple integration procedures. The formalism is expected to be useful especially for considerations such as beam alignment or generation of an external electron beam. Some equations given earlier are repeated for completeness."

The preparation of essentially pure dimethyl selenide for the Isotype Separations Group, Chemistry Division, is described. The compound was prepared by warming a mixture of selenium, sodium hydroxide, sodium formaldehyde sulfoxylate in aqueous solution for several hours at 50°C and then adding methyl iodide. Dimethyl selenide was removed by distillation.

A preliminary study of dispersing agents for thorium oxide has been completed and several of the dispersants have possible uses. Also many of the industrial dispersing agents tested are not usable with thorium oxide due to induced behavior causing balling and caking. The effects of nitric acid concentration have been observed to also effect each dispersing agent.

The error that results when it is attempted to evaluate stress from a reading taken on a single element SR-4 strain gage in a biaxial stress field is discussed. A method is presented for relating SR-4 rosette strain gage readings directly to the biaxial stress state without the necessity of first converting strain gage readings to true strains. Correction formulas are presented for use when single element SR-4 gages are used as rosette elements or as stress gages.

A preliminary mathematical study is made of the maximum expected expansion of barium titanate ceramic. It is noted that there is insufficient physical evidence for a complete answer and some possible mathematical models are discussed and compared.

When a one-half ounce spherical charge of high explosive is detonated over a flat plane bounded by a 5 degree incline, the type of phenomenon encountered depends on the distance from ground zero to a beginning of the incline. If this distance is 48" the wave assumes a smooth contour on the plane. Detailed investigation of the shock velocity above the plane reveals that there is a pressure gradient along the shock front for a considerable region which replaces the usual triple point.

The purpose of the test was to observe the extent and location of corrosion, crud deposits and defects in components of the primary fluid system and its auxiliaries. This observation will allow an estimate to be made of the future behavior of the affected parts. The test also provides for obtaining corrosion products and crud samples for analysis as necessary for planning remedial actions. This test was limited to the 1D Main Coolant Pump which failed November 3, 1958. The pump failed after 2234 hours of operation on "fast" speed and 887 hours at "slow" speed. An inspection for corrosion was not conducted but smear samples were taken and a radiochemical analysis made. This analysis showed the following isotopes were present in the smear sample: Co38, Co60, Fe59, Mn54, Hf191 and Zr95. The upper and lower radial pump bearings and journals were severely scored and galled while the thrust bearing and runner appear to be in good condition.

The purpose of the test was to obtain performance data for the main coolant pumps on fast and slow speed at various coolant temperatures. The 1A, 1B and 1C pump performances on both fast and slow speed were approximately as shown in the manufacture's predicted performance curve. The 1D pump performance was below the manufacturer's predicted flow efficiency, line current and hydraulic horsepower on both fast and slow speeds.

One of the considerations in designing a flat plate fuel element is the resistance of the fuel plates, especially the outer plates in the fuel plate array, to deflection and permanent deformation as a result of pressure differentials. An investigation was recently initiated wit the objective of obtaining preliminary information on the APPR-type fuel element to determine the effect of pressure differentials on the outer plates in the fuel assembly. The APPR-1 fuel element consists of 18 flat composite stainless steel fuel plates, joined to grooved 50 mil thick type 304L stainless steel side plates by brazing with Coast Metals N. P. alloy.

Small Heat Exchanger ORNL #1, type SHE #2, was removed form test stand B after 2071 hours of operation. Thirty-five samples were removed form the entire heat exchanger. The corrosion found on the outside of the tubes exposed to the fluoride mixture ranged to a maximum depth of .004 inches; however, the frequency of occurrence along the tube wall was heavier at the NaK outlet header, which was the hottest area in the heat exchanger. The depth of attack observed on the fluoride side of this heat exchanger was uniform from header to header and did not exceed .004 inches.

Loop L-4-12 was the seventh corrosion test loop operated in HB-4 beam hole at the LITR. The loop was inserted on January 24, 1956, and removed on April 17, 1956. This loop had a titanium core which was attached to the 347 stainless steel loop with special titanium to stainless steel couplings.

A helium coolant purification system was designed for the proposed 800 MWT Pebble Bed Reactor. The purification system will operate on a coolant side stream with a flow rate 1% of the total coolant flow and there are provisions for radioactive and non-radioactive contamination removal.

Sodium hydride dissolves in and reacts with molten NaOH to give an equilibrium mixture of NaH, NaOH, Na/sub 2/O, Na, and H. In the case where there is a gaseous phase (hydrogen) and only one condensed phase, the system is defined by the temperature, pressure, and one composition variable. The equilibrium, H/ sub 2/ pressure, which is a measure of the H/sub 2/ activity within the melt, was determined as a function of the composition of the condensed phase(s) at 600, 700, and 500 deg for equilibrium mixtures with original compositions of 2.5 to 97.5, 5.0 to 95.0, l0.0 to 90.0, and 20.0 to 50.0 mole% NaH-NaOH. The equilibrium H/sub 2/ pressure-composition isotherms obtained by removing measured increments of H/sub 2/ were reproduced by reabsorbing H/sub 2/. Results for the 5.0 mole % NaH mixture were duplicated by starting with an equivalent quantity of either Na in NaOH or Na/sub 2/O in NaOH, and reacting with measured increments of H/sub 2/. The system is discussed in relation to the interdependent reactions involved, the phase rule, the thermodynamics of certain reactions, and experimental techniques employed. (auth)

Portions of the NaOH-NaH phase diagram were studied by means of differential thermal analysis. Under certain conditions NaH will either react with NaOH according to the equation NaH + NaOH in equilibrium Na/sub 2/O + H/ sub 2/ or thermally dissociate according to the equation NaH in equilibrium Na + 1/2 H/sub 2/. Both of these reactions are suppressed by a high H/sub 2/ pressure; and NaH neither reacts nor dissociates to an extent sufficient to affect the results reported. This was evidenced by the fact that changing the H/ sub 2/ pressure above the system in the range indicated did not change, within the limit of error of the experiments ( approximately plus or minus 5 deg ), the temperature at which a phase change was started or completed. Therefore the concentrations of Na and Na/sub 2/O present in the samples must have been small in all cases. Under a high H/sub 2/ pressure, therefore, the system may be considered as essentially binary, consisting of NaOH and NaH. (auth)

A 4-ft-7-in. adsorption column packed with 1/8 in. sodium fluoride pellets was designed to reduce the hydrogen fluoride content of the fluorine being used by the Volatility Pilot Plant from 5% to less than 0.01%. It will be a non-isothermal packed bed with the bas inlet heated to 100 C to avoid plugging and the exit cooed to 25 C for more complete HF removal.