The following report measures neutrons and gammas in solid B4C, as well as measuring H2O containing .5% boron by weight in the lid tank. Quantities measured in the following report in borated water are: thermal neutron distribution along the center line of the source (Z); fast neutron dose vs. Z; Gamma dose vs. Z; and neutron absorption by boron within solid B4C.

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 …

Abstract: "A method has been developed for the determination of sodium monoxide in sodium which depends upon the reaction between sodium and n-butyl bromide in hexane solution. The sodium monoxide does not react with the reagent and can be determined, after the addition of water, by titration. The method is comparatively rapid, requires only the simplest of equipment, and it has the advantage that both oxygen and other impurities can be determined on the same sample."

Abstract: "In a circulating-fuel reactor, the circulation of the fuel cause a damping of power oscillations of the reactor. This is demonstrated under the assumption, that there is no mechanical vibration coupled with the oscillation of reactor power, and that the shapes of the hydrodynamic flow does not vary with time."

Abstract: A study of irradiated and normal Teflon by means of X-ray diffraction, infrared analysis, gas evolution, and visual examination is presented and discussed.

This report follows an investigation with the objectives to improve the design of an existing pilot plant to allow better control of operating variables than was attained by previous investigators, and to determine the effect of leaching time on phthalate recovery.

The following report provides value tables of resonance intervals for various elements and materials.

This report presents data on the absorption of tritium oxide vapor through human skin.

The following report records the study of the optimum pH of the method of the colorimetric dimethylglyoxime for nickel before the addition of oxidant and the concentration of ammonium persulfate needed to insure complete oxidation to higher nickel valence states and thus prevent precipitation of less soluble nickelous salt that was made. Results of this study is presented in Table 1.

Introduction: "This letter is intended to provide a brief summary of the information presently available on the engineering properties of iron-linonite concrete with the view of adapting such concrete with the view of adapting such concrete for use as biological shielding material in a Hanford pile. By reducing materials and fabrication costs, such a adaptation might effect a savings of at least two million dollars per pile over the present iron-masonite laminated shield structure."

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.

A report about investigations of several binary alloy systems of thorium. Some of these alloys containing lead, molybdenum and tin have been prepared in the tungsten arc furnace.

Reconnaissance made of the Red Canyon area with the objective to locate areas favorable to the occurrence of uranium deposits, study the environment of the deposits, and to collect data for regional studies.

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 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.

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

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.

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.

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.

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.

"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 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 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.

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.