Design and construction of remote control equipment for plutonium metal production are described. Criteria for the design of the equipment included the following: rubber gloves were to be completely eliminated; all mechanisms were to be built as integral units to facilitate replacement through use of the plastic- bag technique; no accessory equipment such as switches, valves, piping, or cylinders were to be inside the contaminated enclosure unless required to handle the plutonium; and all units were to be tested in mockups before final design. The chemical process, general layout, and operating function are outlined. Descriptions are given of all mechanical units, electrical systems, hydroxide slurry systems, ventilation systems, and chemical tanks and manifolds. (W.L.H.)

The production yields of hydrazine by various ionization methods are compared. The maximum value of M/N (number of molecules reacting per ion pairs) for electric discharge was 0.25 and for beta particles on liquid ammonia, M/N = 0.31. A 1-Mev reactor could produce 1.6 kg of hydrazine per hour if M/N = 0.04 as determined by alpha particles on liquid ammonia. About 300 ev of energy were needed to form a hydrazine molecule. (C.J.G.)

A tentative nickel-plutonium constitutional diagram was based on data obtained by thermal analysis, metallography, and x-ray-diffraction techniques. The systema is a complex one with the following important features. Nickel is soluble in epsilon plutonium, extending the epsilon field to 4.3 at.% nickel at 465 deg C. Nickel and plutonium form six intermetallic compounds, PuNi, EnNi/sub 2/, PuNi/sub 3/, PuNi/sub 4/, PuNi/sub 5/, and PuNi/sub 9/. The compound PuNi/ sub 5/ forms congruently from the melt at approximately l300 deg C, whereas the other compounds form peritectoidally. The extended epsilon field terminates in a eutectoid reaction at 415 deg C and l.5 at.% nickel. Epsilon plutonium and the compound PuNi form a eutectic system at 465 deg C with a eutectic composition of l2.5 at,% nickel. Nickel and the compound PuNi/sub 9/ form a eutectic system at l2l0 deg C with a eutectic composition of 92 at.% nickel. Plutonium forms a limited solid solution with nickel.

It has been found relatively easy to form uranium in the gamma phase temperature range by hot pressing, forging, or extrusion. The metal is quite plastic and flows readily to form a shape. Several temperatures from 800 degree C to 1000 degree C were investigated. No forming difficulties were experienced with the metal at the several temperatures concerned. The major difficulty in gamma phase hot pressing or extruding was associated with the tools. Metals or ceramics were not successful as tools for one or more reasons concerned with: lack of hot strength, reactions with the uranium, failure in thermal shock, and tendency to spall. Graphite was found to be the best material available, but it is not entirely satisfactory because of low strength. Uranium formed in the gamma phase possesses some refinement of grain structure as compared with as-cast metal; however, the grain size is quite large. No physical properties of the gamma phase formed metal were determined.

The basic scheme under consideration in this research on stability of closed-loop of the Mark I machine is one in which a voltage proportional to the magnitude of the rf fields in the cavity acts to control rectifier voltage output. It is recognized that such is not the only scheme for maximization of output which may be conceived, but only what seems to be a logical and direct way of attaining such an objective.

The complexing of lanthanum by various anions and weak acids was investigated by observing the light absorption of the complex formed with thenoyltrifluoracetone (TTA). This species showed the properties needed for a satisfactory specgtrophotometric method of analysis.

Technical report covering chemistry of source, fissionable, and structural elements, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, and instrumentation at the Oak Ridge National Laboratory for the period ending September 30, 1950. [From Abstract]

Technical report investigating the distribution of rare earth elements between a liquid bismuth-uranium solution and fused KCI-LiCi mixtures. Report warrants further research on the liquid bismuth-uranium-fused salt system due to the benefit of continuous fission removal processes.

The heat studies include: automatic time-delay relay for Panellit System; heating of fuel rods; installation of a thermocouple slug; effect of tube length and annulus on tube power; pressure drop film studies; full scale mock-up; flow tests; front to rear enrichment of B, D, and F piles; electrical analog studies; studies on thermal and biological shields; and recirculating system heat exchangers. Some of the topics discussed in the water studies section are: the 100-D flow laboratory; film formation test apparatus; can difference test; Calgon chemical purge for film removal; flow laboratory recirculating studies; slug jacket abrasion at high flow rates; sodium dichromate elimination tests; process water studies; and corrosion studies. The mechanical development studies sections includes the following subjects: Sphincter seal test; ball corrosion test; horizontal control rod conversion study; P-13 removal; chemical slug stripper; temperature monitoring of tube outlets; slug air weigher; slug damage; process tube replacement; crossheader improvement; water cooled test hole facility; 189-D test laboratory; creep in process tubes; charging and discharging machines; flapper nozzle assembly test; horizontal rod gland seal test; and horizontal rod mock-up test.

This report is a monthly progress report for the 100 Area of the Hanford Reservation, covering work by the plant assistance group and engineering development group. It summarizes activities of these groups in support of the production reactors in this area.

None

This is a memorandum from the Hanford Operations Office about the possibility of tritium wastes escaping into the atmosphere. The waste which is disposed of in burial grounds eventually migrates to the Columbia River where it evaporates into the atmosphere. Also included in this memo is a statement of an error in the units of some data compiled for the monitoring of the tritium wastes. (MB)

This report discusses particle size measurements with a modified cascade impactor of the particulate matter in the dissolver off-gases during the period of maximum gas evolution, and during the air sparge of the dissolver solution after the completion of the dissolving cycle which indicate that the mass-size median of the particles was less than 0.1 micron in both cases. The measurements were made, unfortunately, at a time when the efficiency of the silver reactor upstream to the sampling point was low enough to permit appreciable amounts of iodine through to the cascade impactor. The samples were therefore permitted to decay for thirty-five days before the relative amounts of radioactivity on the stages of the impactor and the follow- up filter paper were evaluated. The size of the particles obtained, 0.1 micron, should be considered primarily as an order of magnitude rather than an absolute value, because the cascade impactor (as well as any other impaction device) can not give an accurate value for the particle size in this size range.

This document describes the scope of the C-431-B Reactor Production Facility. In dealing with the broad phases of the project, it includes the Sections ``A`` (Scope Modifications) of the approved Design Criteria, modified to ensure correctness to date. Location of the facility has been set as shown on the site map in HDC-2101, designated site number one. Included in Project C-431-B are the 105-C Building, including within that building facilities previously located in the 1608 Building, a contaminated effluent crib adjacent to 105-C, and gas facilities using the 115-B Building interconnected with 105-C. Also included are an oil shed, a thimble storage cave, a badge house, and an exclusion fence. Building services and process lines will be considered part of the project to a location nominally five feet outside of 105-C.

This is the monthly 100 areas technical activities report from the engineering division for the month of March 1951. It reports on engineering activities related directly to the different production reactors, and gives progress reports on various engineering projects which are in development by the engineering group.

None

Binary alloys of uranium with 38 elements in the range 0.01 to 1.0 at.% were made. Three alloys having nominal compositions of 0.01, 0.1, and 1.0 at.% were made with most of the elements, and in addition, 12 ternary and quaternary alloys were made. The alloys were cast, rolled to 7/8-inch-diameter bars, heat treated, and examined for grain size.

From introduction: "The work covered in this report is a portion of the experimental research undertaken for the design of a uranium-containing metallic fuel rod for operation in air at 1090 C...This report deals with that phase which involved the testing and evaluation of various metals as barrier costs between uranium alloys, and low-carbon steel. The work is of a preliminary nature and is concerned more with a comparison of the various barrier metals than with the acquisition of numerical data, e.g., diffusion coefficients."

Abstract: A comprehensive study was made of various fractionation systems for the fractional separation of barium-radium mixtures. The most efficient and simplest fractionation scheme was chosen on the basis of the thermodynamics of separating the constituents of mixed crystals and of the combining fractions in a system of repeating composition. This scheme was applied to the separation of barium and radium by utilizing the countercurrent batch fractionation of the chromates. The chromate procedure was evaluated by a comparison with the classic methods which employ the fractional crystallization of the halides. The chromate method is more practical on the basis of radium enrichment per fractionation step, control of precipitating conditions, simplicity, and speed of operation.

Introduction: "A number of determination have been made of the half life of polonium-210 by calorimetry. Counting affords an entirely different method of determining half lives and requires only a small amount of activity. Therefore for comparison a half-life determination by counting was undertaken with a sample of approximately 0.5 millicurie of polonium."

From summary: "Various thermal and mechanical properties were measured for sintered tin oxide-matrix compacts which nominally were composed of 99 per cent by weight of tin oxide, SnO2, and one per cent by weight of zinc oxide ZnO...The tin oxide body might be expected to give good service under conditions of severe thermal shock and in an oxidizing atmosphere at temperatures up to 1500°F."

Report discussing progress made by the Chemistry Division (Section C-1) of the Argonne National Laboratory for the months of April, May and June, 1951. Information is divided into "Nuclear Chemistry and Radiochemistry" and "Basic Chemistry".

Abstract: "Steady states decomposition product partial pressures of water exposed to an epithermal neutron flux of about 2 x 10-11, at 235F, were 0.4 to 0.65 psi. Recombination studies were made by adding hydrogen and oxygen gases to water under irradiation at different temperature and flux levels. The data show a significant effect of temperature on the rate of pressure drop of the added hydrogen and oxygen. In operating at two flux levels, 1.2 x 10-11 and 2.0 x 10-11, no difference in the rate of pressure drop with flux could be detected with the instrumentation on the test apparatus."

Report discussing progress made in metallurgy by the Ames Laboratory during the the term from October 1, 1950 to March 31, 1951.