"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.

In conjunction with Gas-Cooled Reactor heat-transfer studies, local and mean heat-transfer factors are predicted from the heat transfer-mass transfer analogy using subliming naphthalene in air. Experimentation was conducted on 1-in.-dis septafoil rods in a 4-in. -dis flow channel with rod center-to center spacings of 1.10, 1.25, and 1.40 in. at a Reynolds modulus of approximately 60,000. Ratios of local mass transfer to mean mass transfer for a given rod vary as much as from 0.7 to 1.3 (outer rod, 1.10-in. spacings). Mean values of the mass-transfer factor are, in general, above that predicted by the correlation j-0.023 NRe^-0.2; as much as 46% got the outer rod t 1.25-in. spacing. The data indicate that for maximum mass transfer and minimum variation of the mass-transfer factor, an optimum rod spacing exists; the best observes is at 1.40-in.

The assembly of a second thorium oxide slurry corrosion test facility, loop BS, has been completed and 2010 hr of operation on slurry have been logged. This second test loop has proved satisfactory from an .operational standpoint. Corrosion data and operational observations are given for six thorium oxide slurry runs made at 300 C in 100A pump loops BS and CS. A new development model of the rotator for an in-pile slurry toroid is described.

The distillation method (Argonne Sampler) for the analysis of sodium oxide in NaK was used to calibrate a plug indicator. The description of the equipment, procedure, and experiences with the Argonne Samplers are presented in great detail to aid future users of this method. Although this method is not very precise, it has been thoroughly checked out and is recommended as a standard means for sampling and analysis for oxide in liquid metal systems. (auth)

Data are presented for all toroid runs which circulated aqueous thorium oxide slurries between Aug, 1054, and October, 1956. In addition, a tabulation of the properties of numerous thoria preparations is presented.

Second and third tests were conducted on an expansion bellows and Zircaloy-stainless steel transition joint assembly, duplicating that used in the core-pressure vessel assembly of the HRT. The assembly was exposed for 1140 hours in the second test and and 167 hours in the third to a solution containing 0.04m UO2SO4, 0.02m H2SO4, and 0.005m CuSO4 in a 100A dynamic corrosion loop under conditions simulating reactor startup, shutdown, and steady-state operation. Results indicated that the transition joint assembly as tested was mechanically sound and leak-tight. Pit-type corrosion continued on the expansion bellows where the upper retaining tangent contacts the bellows. Results are included of specimens exposed to the circulation solution during transition joint and bellows test.

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.

This is the sixth in a series of interim reports describing various phases of the study of fuel element rupture kinetics and mechanisms. Previous reports issued are: No. 1- Experimental Methods and Procedures, HW-61378, No. 2- Coextruded Rod Elements with Pinhole Defects, HW-61379, No. 3 - Mechanism of the Uranium-Water Reaction, HW - 61799, No. 4 Coextruded Tube Elements with Pinhole Defects and Various Annular Spacings, HW- 62348, No. 5- Comparison of In-Reactor and Ex-Reactor Ruptures, HW-62766. This work is being done in cooperation with the Fuel Element Design Operation of the Hanford Laboratories Operation. J. W. Goffard has been particularly helpful in supplying samples and useful discussions of the results.

The majority of two-phase flow problems involving equations of state are solved by use of point-wise utilization steam table values. In this manner, problems involving the use of the various flow equations of continuity, momentum and energy are generally forced into iterative solutions. Considerable effort towards the development of an analytical expression for the state equation seems indicated so as to simplify the analysis of two-phase problems, particularly apparent in the analysis of systems undergoing phase transformation as demonstrated by the significant difference between simple theory and experimental critical flow determinations. The assumption of homogeneous, equilibrium mixture is indicated as a first attack upon the problem.