"A method is outlined for calculating the trajectories, through the magnetic field of the following magnet pair of positive and negative particles of different momenta produced in a target. Representative trajectories were computed by this method and are given numerically."

The original goal of this investigation was to compare the thermodynamic characteristics of the gases in and behind the shock fronts in gases at initial pressures in the millimeter range and to compare these characteristics in the geometries of single and double discharges. The shock fronts were not visible, so it was not possible, at these pressures, to get visual data from the shock front itself. The parameters giving the properties of the gases were faces. Measurements made with an image converter camera (which is still in the development stage) agree well with these made with a photomultiplier tube. Differences are observed between the front velocities in the cases studied. These are of the order of 3 to 15 per cent. Considering the nature of the shot to shot fluctuations in the discharges and the inductance variation between the single and double discharges represent a physical difference. The mathematical treatment which says that two equal strength colliding with a wall behaves, has not been shown to be inadequate by this investigation. It was hoped that a stronger confirmation could be fien to the theory, but the accuracy of the data does not warrant it.

The corrosion of INOR-8 and Inconel dissolver components used in the fluoride volatility process for the dissolution of zirconium with anhydrous HF in molten salts was investigated. Ten dissolution runs were made using simulated subassemblies formed from Zircoloy-2. The dissolver and components were made from INOR-8. Both the dissolver vessel and draft tube were examined several times during the series of runs. The solids which formed at different areas in the system were also analyzed. The results showed that the corrosion of the INOR-8 dissolver was greatest at the salt-off gas interface and at the HF gas inlet. Almost all of the corrosion took place during run 10 when no zirconium was present. Portions of the dissolver were cleaned after run 10 and sent to BMI for evaluation. The results of the Battelle metallographic examinations of the portions are included along with several photographs. The results with Inconel tubes in the copper-lined hydro-fluorinator confirmed the observations that the liquid gas interface areas were the most susceptible to attack.

Since the inauguration of the Off-Site Animal Investigation project n 1957, there has been one annual report rendered as of 30 June 1958. this is the second annual report dated as of 30 June 1959. The objectives of the project have been unchanged during the past year. These are (1) to enhance the Nevada Test Site/off-site rancher relationship through an active investigation project in their interests, and (2) to provide further information as to the status of the off-site animals in their environment, with special emphasis on their radioactive isotope uptake from fall-out. isotope uptake of the animals is being emphasized as well as the gross and microscopic histopathological examinations. Two year's existence in an area of radio-contamination where a full fission spectrum of isotopes can be found, where radiation background reading range from 1/2 mr per hour to 1 = per hour, has produced no noticeable effect on the animals.

The purpose of the test was to determine the neutron flux level in a BF3 counter well during the second performance of DL-S-225. The measured activity of the irradiation brass bolt was due entirely to the radioactive decay of Zn65. The thermal neutron flux in the BF3 counter well during the second 1000 hour run was calculated to be 2.5 x 10(9) neutrons/cm2 sec.

Results are summarized on theoretical considerations of the excited states of the Ca isotopes, experimental studies of the level structure of Ca42 and Ca44, studies of the production of circularly polarized bremsstrahlung by beta rays, the Moller scattering spectrometer, and the Moller scattering coincidence experiment.

The purpose of the test was to determine the radiation levels inside the concrete enclosures but outside the reactor plant containers after shutdown following plant power operation. Radiation levels at the survey points in the 1-AC and 10BD Boiler Chambers Enclosures and in the Reactor Container Enclosure indicated that no significant radiation hazards were present approximately 25 minutes after all rods had been inserted. The radiation levels approximately 4 minutes after shutdown at the survey points in the Auxiliary Chamber Enclosure indicated that several points were above background, the highest test level being obtained in contact with the East Auxiliary Chamber container drain pipe.

The purpose of the test was to check the extraction crane rails in the area of the reactor pit for level and parallelism. The west extraction crane rail exceeded the allowed tolerance of 1/32 inch at only one location. The elevation of the north bumper was out of tolerance by 1/64 inch. The east extraction crane rail was consistently lower than the west rail by as much as 8/64 inch. The east rail was parallel with the west rail within allowable tolerances over the length tested except at one location where the transit was located, approximately 41 feet from the north bumper.

The purpose of the test is to determine the reason for the decreases in the liquid levels of the reference chambers serving the reactor plant remote liquid level indicators. The remote gages and the local liquid level gages agreed closely for the Reactor Plant Component Cooling Water Expansion Tank and the Coolant Discharge and Vent System flash tank and blow-off tank. There appeared to be no loss of water from the D/P cell reference chambers for these two systems over the period of the test. There was no definite indication of leakage from the Valve Operating System reference chamber, however, the differences between remote indicator readings and the sight glass readings are attributed to sticking of the ball check valve on the upper sight glass, inaccuracy of the readings and instrument error. It is recommended that he lower shut-off valve on the upper sight glass be cleaned and reopened prior to reading the sight glass to ensure that the ball check valve is not stuck in the closed position. No lead age was found in any of the level indicating systems.

This is the thirty-seventh progress report of the Laboratory for Nuclear Science at the Massachusetts Institute of Technology. Progress during the period of June 1, 1955 through August 31, 1955 is reported on: (1) Chemistry of the fission elements group, (2) Nuclear chemistry (inorganic) group, (3) Nuclear chemistry (organic) group, (4) Cosmic ray group, (5) Elementary particle scattering group, (6) Neutron physics group, (7) ONR generator group, (8) Radioactivity group, (9) Cyclotron group, (10) Synchrotron group, (11) Theoretical group, (12) Personnel listing.

Information concerning the transformation kinetics of the gamma solid solution of uranium-base alloys is important. Accordingly, the metastability of the gamma phase was investigated for nine uranium-rich alloys of the U-Mo-Pt, U-Mo-Nb, and U-Nb systems. Samples were encapsulated in Vycor bulbs, solutions treated at 1000 decrees or 1050 degrees C, quenched to and annealed at temperatures between 600 degrees and 300 degrees C. Techniques employed to follow transformation included metallography, resistivity, X-ray diffraction and hardness. A difference exists between the TTT curves for the same alloy determined by different techniques. However, this is readily explained. The body-centered cubic gamma phase of the U-Mo and U-Mo-X alloys decomposes eutectoidally to form alpha and epsilon, an ordered structure. The eutectoid temperate is about 575 degrees C in the binary system. In the U-Nb system the gamma solid solution decomposes monometrically (or eutectoidally) to a product of alpha and another niobium-rich gamma phase. Alpha uranium has characteristic low solubility for either of the alloy components. The nose of the TTT curves for the U-5.1 wt % Mo and U-10 wt % Nb compositions exists at about 550 degrees C and 0.1 hour. Minimum times for transformation are longer for the other alloys. Rather …

Progress is reported in studies on (1) injection tables, (2) radon escape from bone containing radium, (3) on the question of th228 translocation in Ra228 dogs, (4) further studies on the metabolism of Th228 and its daughters, (5) veterinary group report, (6) hematology observations, (7) biochemistry, (8) pathology and detailed radioautography report, (9) radioautographic studies of Pu and RdTh teeth, (10) effect of parathormone on the deposition of Pu in rats, (11) speculation on the toxicity of RdTh and MeTh relative to radium, (12) autoradiographic and histopathologic studies of beagle puppies administered intravenously with Sr90, (13) plasma Fe study, and (14) Cr51 tagging RBC study.

This report summarizes the test work done to evaluate the column ion exchange process for extraction or uranium from Grants acid leach liquors.

Leach liquors produced from Utex ore by cold leaching, hot leaching and pugging proved amenable to the ion exchange process. In addition, a resin-in-pulp system was operated using the Lucite Winchester sells on Utex pulp produced by cold leaching.

Uranium extraction of 95% has been obtained from samples of Temple Mountain ore by a cyclic test procedure in which the new feed was not roasted. This procedure involved acid leaching the ore, flotation and roasting of the carbonaceous material, and acid leaching the roaster calcine.

Leaching tests indicated high recoveries could be obtained by use of large quantities of sulfuric acid and boiling for relatively long periods. Filtration rates were satisfactory but large settling areas would be required to wash and thicken before filtering.

The causes for loss of uranium originally adsorbed on strong base anion exchange resins from Rand cyanide residue leach liquors after prolonged passage of such liquors through resin columns were investigated.

Leaching of high carbonite Belgian Congo uranium ores with sulfuric acid and recovery of the uranium from leach solutions by uranous phosphate precipitation are described.

"A series of high urania-content glasses were fiberized and examined for high-temperature strength properties. One glass, RX360 containing 60% U/sub 3/O/ sub 8/ by weight, had better high-temperature tensile properties than any glass previously reported. It was observed that many of the glasses studied separated into immiscible phases and that the fiberizable glass phase had lower U/sub 3/O/ sub 8/ content than the base compositions. A physical analysis of crystal structures of the devitrification products from the nuclear fuel glasses indicated that most of the crystals consisted of uranium oxide in a reduced state. By adding O/sub 2/ to molten glass, it was possible to eliminate most of this devitrification. By elimination of crystals, the fiberizing of the glass was more uniform and the glasses produced had more consistent physical properties."

"Acoustic energy generated by mechanical or electrical signals and its effect on pool boiling of isopropanol were studied. Daring the course of the investigation, a method was devised to determine the amount of heat-transfer surface wetted by the boiling isopropanol. Plots of heat flux versus temperature difference for each frequency showed that the acoustic energy did not significantly affect the heat flux at burnout, but slightly increased the critical temperature difference. No general effect of frequency variation was found even at the frequencies of the "boiling songs" of isopropanol. The over- all effect of the acoustic energy was to disturb the vapor tending te coat the heat transfer surface. This was most evident from the absence of film boiling even at temperature differences far above the critical temperature difference. The application of alternating current to the boiling system gives promise of a self-regulating method to increase boiling heat transfer when required, and is the most significant new finding of this investigation. Two pertinent Russian papers were translated and are appended."

"A survey of the current theoretical picture of plasma containment in cusped magnetic configurations is presented together with a mention of the points of contact which exist or might soon be made to exist with experiment. A theory of containment was developed which is applicable to the whole range of plasma densities from a tenuous plasma in an essentially vacuum magnetic field to a fully developed plasma which completely excludes the magnetic field from its interior. Also presented are cursory accounts of the situation with regard to stability, cyclotron radiation, and methods of creating this type of plasma configuration."

"Design and fabrication techniques were improved so that the large area image intensifier now performs well in image intensifier systems for photographing nuclear tracks. Two successful samples meeting most of the objectives were completed and started in circulation among members of the AEC Image Intensifier Committee for evaluation in systems to record nuclear tracks. Except for a reported long decay in the P-15 phosphor performance was quite good. Resolution, gain, and background requirements were met. Magnification was still high (1/6.5 compared to a design objective of 1/8) but can be lowered to 1/8 by a straightforward mechanical change. Evaporated layers of thallium activated rubidium and cesium iodide were improved and further evaluated. Improved control of color and persistence was obtained. Efficiency as high as 1/3 that of P-11 phosphor was obtained in some samples. The current test series confirmed earlier results that an increase in cesium iodide content shifts the emission spectrum towards the yellow. Burn-resistance and light output was poorer for the cesium enriched phosphors while decay time was decreased.

"The design of the nuclear track intensifier was further analyzed to compare performance with design objectives. A preliminary analysis of the electron optics showed that the tube design suffers a small degree of astigmatism, which is increased in actual tabes by misalignment of parts, One tube was successfully completed and tested. Transit time of electrons from cathode to screen was determined to be 2.5 x 10/sup -8/ sec, 0.5 x 10/sup -8/ sec. Decay characteristics of several standard phosphors were measured. In the phosphor development phase, a latin square test was designed to evaluate combinations of thallium-activated rubidium iodide and cesium iodide phosphors under various evaporating conditions. Data were taken on various tests and analyzed statistically. On target samples submitted for tube evaluation, a reaction, which reduced light output, occurred between the aluminum and phosphor during vacuum bake. Oue image tube prepared with an alkali iodide mixture showed 10 to 25% improvement in screen resolution as compared to a P-11 screen."

"Development of a nuclear track image intensifier which is to have a cathode dia. of 83 in. and an output screen dia. of 1 in. is reported. Spherical faceplates for the intensifier which were etched to a thickness of 0.025 in. over a dia. of 80 in. withstood a pressure differential of 2 atm. Techniques were developed to measure spectral energy distribution, phosphor burn characteristics, phosphor efficiency, and phosphor persistence. Thallium- activated RbI and CsI were evaluated for use in the first stage of the image intensifier system. A color shift toward the yellow was accomplished in rubidium iodide phosphor by increasing the mole % of Th activator. Burn varied widely in different samples."