From abstract: "The effects of solution concentration and acidity on extraction of uranium by diethyl ether have been investigated... The approximate solubility of vanadium pentoxide in nitric acid was determined."

From abstract: "Results are presented which suggest the possibility of satisfactorily extracting uranium from pitchblende feeds with neutral ether, without the necessity of removing sulfate, by the addition of a sufficient quantity of iron to the feed." Other factors' effects on extraction were tested and arsenic was traced throughout extraction.

This quarterly progress report discusses topics of research and experimentation at the Oak Ridge National Laboratory, including inorganic chemistry, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, chemistry of the solid state, instrumentation, reactor chemistry.

Abstract: "A magnetohydrodynamic model of a plasma-magnetic field instability, using liquid sodium, has been observed. The growth rate and wave length of the Taylor-type acceleration instability was observed to be in agreement with the theory of Kruskal and Schwarzschild."

Introduction: This note describes briefly the current concept of the experimental program on source development for mirror machines. There are two major facilities involved: (1) A comparatively small machine whose code name is "Guppy", and, (2) A larger d.c. mirror geometry whose code name is "Waldo."

Abstract: "A magnetohydrodynamic model of plasma-magnetic field instabilities, using liquid sodium, has been observed. The growth of flutes in the mirror geometry was observed for the case of [beta] = NKT/H²/8w = 1."

This report for September, 1947 describes progress regarding ore dressing and pyrometallurgical studies, chemical work, analytical work, identification work, and future work

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 …

The following report discusses measurements for slow and fast neutrons from cadmium coated ionization chambers.

Abstract. A series of paired explosions in a salt mine near Winnfield, Louisiana, has been conducted to test a theory by Dr. A. L. Latter concerning seismic decoupling by underground cavities. The theory predicted a decoupling of about 100. Free-field and surface measurements from an explosion in either a 6-ft- or a 15-ft-radius spherical cavity were compared with similar measurements from a completely tamped explosion. Shot sixes were from a 10 lb up to a few tons. Surface measurements were made out to 100 km and covered the frequency range from 0.05 to 100 cpa. The experiment confirmed that decoupling does occur. The actual decoupling factor as a function of frequency is presented and compared with the Latter theory.

Abstract: "Crystal system, crystal habit, and principal refractive indices, of uranyl hydrogen phosphate tetrahydrate, uranyl ammonium phosphate trihydrate, and uranyl phosphate tetrahydrate are reported. A procedure for differentation of these three compounds using this data was developed."

Report discussing "the production of beryllium by the metallothermic reduction of its fluoride...Charges of BaF2 and Mg reacted smoothly when heated by induction in graphite crucibles and on continued heating the metal and slag separated fairly well. It was found that an addition of CaCl2 to the top of the charge facilitated the separation a great deal. Very clean, massive metal has been produced by this procedure."

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.

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 this paper we solve for the diffracted wave which results when a weak hydromegnetic shock impinges on a rigid perfectly conducting half plans."

"A survey is presented of the theory of confinement in open-ended systems (such as mirror machines and cusped geometries) together with the slight amount of experimental confrontation with theory that exists at present."

Quarterly updates on nuclear chemistry, bio-organic chemistry, general chemistry, chemical engineering (process chemistry).

Through the years, considerable effort has been expended in studies of the explosive reactions sometimes observed in the dissolution of uranium-zirconium alloys in nitric acid. It has been shown (1) that such reactions result from the rapid oxidation of finely dived solids released by the preferential dissolution of the metallic matrix. The explosive portion of such solids has been identifies (1) as an intermetallic compound with the approximate composition UZr2. This compound, referred to as the epsilon phase in previous work, has more recently (2) been termed the delta phase. The latter designation will be employed here.

This technical report represents the final design for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming fro the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to the steam generator. Because of radioactivity the unit will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shutdown it will be necessary to allow time for radioactive decay before the unit will be accessible to personnel. Because of inaccessibility and possible long periods allowed for decay time, it is imperative that the unit give trouble free operation. During periods of shutdown, the internals should have easy access for inspection and repair if necessary so that down time is held to a minimum. The steam generator is designed to generate superheated steam using liquid sodium from the intermediate heat exchanger as the heat source. Its basic design is a shell and tube unit made up of three difference sections: (1) a …

Introduction: This volume deals principally with the chemical analysis and the stress analysis for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The work presented is an extension and modification of the analysis presented in the preliminary design report. The chemical analysis covers the sodium cover gas system and the effects of sodium-water reactions in the event of a leak in the steam generator. Considerable design work was done in an effort to maintain the integrity of the steam generator vessel under maximum leak conditions. The method of sizing relief valves for each unit under varying leak rates is presented in this text and operation of the unit for the various leak rates is resented in the Operation and Maintenance volume. The stress analysis section covers those thermal transients which would be physically possible with this intermediate heat exchanger and steam generator design. Attention has been given to methods of operation which would minimize the magnitude and frequency of thermal shocks. Certain areas have been studied in detail where thermal stresses appear high. This report also includes a structural design basis for handling stress analysis of combined mechanical, hydrostatic and thermal stresses and conditions …

Introduction: Sodium Components Material Specifications. Twenty-three material, inspection and welding specification are presented for the various parts of both the intermediate heat exchanger and steam generator. Tables indicate the applicable parts and assemblies to which these specifications shall apply. For other parts, where the material requirements are not severe, the ASTM or other indicated specifications shall apply.

This technical report contains the operation and maintenance specifications for the intermediate heat exchanger and the steam generator. The report contains eight sections: (1) General Information, (2) Shipping and Installation, (3) Operation Procedures, (4) Scram and Casualty Shutdowns, (5) Leaks, (6) Instrumentation and Control, (7) Maintenance, and (8) four Appendixes (a) Boiler Water Chemistry Recommendations, (b) Final Concept Drawings, (c) Industrial Nucleonics Literature on Liquid Level Detector, and (d) Sodium Purity Control Recommendations.

"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."

This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion,