In this paper we are concerned with the potentials and electrical currents flowing at an interface between two phases as a result of chemical reactions which promote selective ion migration. Although our immediate concern is an explanation of the available results on smelting, a sufficiently broad understand requires that we go far beyond this limited results and bring together the findings from many related fields. We first must consider the diffusion of particles across an interface, which for convenience we will speak of as a membrane since convection currents usually stir both phases except for a thin boundary layer.

This study is concerned with a class of circuits which employs two tubes in a series connection--sometimes referred to as the stacked-tubes connection. This study will be concerned with two configurations that have shown considerable promise in the field of high speed circuitry. In Part I a configuration called the dynamic plate load amplifier is dealt with. In Part II a configuration called the White cathode follower is examined.

From introduction: This report is a summary of geologic information obtained by the USGS at Dolomite Hill, Nevada.

An analysis to screen the various particle-collection systems which might be used for sampling the upper atmosphere with a rocket sampling vehicle has been undertaken. Although the current model of the Goetz Aerosol Spectrometer is not suitable, a high-flow-rate sampler of this general type, if it can be designed, appears promising. The design of such a sampler will be undertaken in future work. If a workable design is possible, this method would appear to be the most promising of all.

The relation between the maximum permissible transverse energies of particles that can be focused, the azimuthal energy, and the beam width is discussed relative to Megatron coil design. It is shown that deep potential wells for focusing can be obtained only at the expense of a narrow beam. (C.J.G.)

The first series tests in the KER-REP-1 loop proved that a fisssion product contaminated loop could be decontaminated to a safe level for contact maintenance. The second series of tests ere scheduled for a more thorough evaluation of these processes includes specific decontamination factors, process corrosion rates, loop activity reduction factors (loop decontamination factors), and any preferential decontamination which may be present.

When following the performance of automatic and semi-automatic equipment that is left unattended for extended periods of time, it is often desirable to be able to check this equipment by remote means. A convenient vehicle for such a check is the telephone since nearly all locations have or can have a telephone extension installed. The check of the equipment may be made as simple or extensive as desired, with the outcome of the check represented by a relay condition, for example. The condition of the relay is then transmitted to the interrogator over the telephone line by means of the presence or absence of a tone.

Report documenting the investigation of cosmic and terrestrial background radiation. "Remeasurements in many locations furnished estimates of dosimetric increase in terrestrial levels due to fallout. Radiation measurement sin residential dwellings in he New York metropolitan areas are described" (p. 1).

This report analyzes the High-Energy Electrostatic Plasma Gun, which is to be used for propulsion.

The purpose of the survey was to determine the radiation levels in the 1 D Boiler Chamber during plant operation. The conclusion of this survey is that the radiation level in the 1 D Boiler Compartment with the 1A, 1B, and 1C Main Coolant loops in service at approximately 100 per cent power ranged from .03 MR/HR to 6.0 MR/HR.

Report containing information regarding the design of the Tory II-A nuclear ramjet engine, and descriptions of its locale, test program, and possible hazards.

Instrumentation shall be provided as shown on the attached drawing, SK-1-26835 for Confinement System Control. The Primary objective of the confinement system shall be to provide maximum possible confinement of contamination, consistent with building limitations, in the event of any contamination, consistent with building limitations, in the event of any credible reactor accident resulting from equipment failure or reactor mis operation.

The purpose of the test was to determine the responses of the plant when subjected to load transients exceeding the design magnitudes, and to determine the maximum load changes, positive or negative, that the plant can sustain. The reactor plant responded satisfactorily to all load transients. The only limits exceed were the pressurizer high and low level alarm points. The magnitude of the transients and the time required for the plant to return to equilibrium was dependent upon the size of the the load change. The pressurizer spray was effective in reducing reactor coolant pressure positive surges; however, this resulted in larger negative surges than when the spray valve was closed.

This specification is specifically designed for the procurement of Zircaloy tubing to be used in the of swaged, UO fuel elements, an, and the Pu fuel elements for the Plutonium Recycle Test Reactor. Requisition G-385923 contains the following information pertinent to this specification: 1. Dimensions and dimensional tolerance. 2. Source of zirconium sponge and conditions for us of Zircaloy scrap. 3. Inspection requirements. 4. Shipping instructions.

The purpose of the test was to determine the direction and magnitude of any drift in the temperature sensing elements and the receiver-indicating units for the primary loop and pressurizer resistance thermometers. To obtain intercalibration data for various temperature sensing elements in the primary coolant system. To obtain data on the difference between the calculated signal generated by the BF-3 counters, considering the known rate of decay of the PO-BE source, and the measured values. Determination of temperature sensing element and instrumentation drifts could not be made due to a lack of comparative data. Five temperature intercalibrations were performed using the calibrating Tc resistance thermometers as a standard. The data obtained from the nuclear instrumentation was too erratic to form any conclusions.

The purpose of the test was to determine the direction and magnitude of any drift in the temperature sensing elements and the receiver-indicating units for the primary loop and pressurizer resistance thermometers. To obtain intercalibration data for various temperature sensing elements in the primary coolant system. To obtain data on the difference between the calculated signal generated by the BF-3 counters, considering the known rate of decay of the PO-BE source, and the measured values. Of the 62 core thermocouples observed 19 were either reading less than 400 F or were reading in excess of 20 F from the calibrating thermometer temperatures. In each case the thermocouple was considered defective. The remainder were within 2 per cent of the calibrating thermometers. The primary loop (Norwood Indicators) resistance thermometers all read with 0.2 percent of the calibrating thermometers. No conclusion could be made for the pressurizer temperature instruments or the boiler Tb resistance thermometers, except that the 1A boiler temperature varied 10 F to 20 F from the 1Band 1C boiler temperatures. A laboratory calibration of this instrument will be made. The data obtained from the source range nuclear instrumentation was too erratic to form any conclusion. No drift evaluation on …

Considerable interest has developed in the use of ion-exchange in the nuclear energy field in the last decade. Aside from the obvious use of providing demineralized coolant water for reactors, the projected uses of ion-exchange include the recovery of fission products from aquaeous waste streams and the separation and purification of fissionable materials from spent reactor fuels. The latter process may be incidental to the over-all operation, as is the case with the Purex anion exchange facility, or it may be the prime separation process, as may be the case in the recovery of Pu or U from spent power reactor (PRTR) fuel elements.

The purpose of the survey was to determine the radiation level in the Turbine Generator Services Building, around the Fuel Handling Canal, in the limited access areas of the reactor plant containers and on the boiler container roofs during plant operation. The test was performed with the plant at approximately 100 per cent power with three loops (1A, 1B, and 1C) in service. The radiation levels of the areas surveyed with a few exceptions were essentially background (.03 MR/HR). These exceptions were the Auxiliary Chamber and the limited access areas between the containers. The highest radiation level obtained in the survey was >2500 MR/HR at the reactor chamber walkway.

Abstract: "Tungsten-rich alloys, developed for use at temperatures up to 2000F, exhibit ductility, fabricability and joinability not found in commercially-available materials. An envelope type of microstructure was produced in compositions containing at least 90 wt% tungsten by liquid-phase sintering of cold-pressed powders in hydrogen. At room temperature the alloys could be rolled extensively, and tensile elongations up to 25% were noted. Strength properties of a W-Ni-Fe base were improved by small quaternary additions. The ultimate tensile strength of a 90W-4.8Ni-3.2Fe-2Ru alloy was 46,700 psi at 2000F, compared to 30,000 - 35,000 psi for unalloyed tungsten or W-Ni-Fe; the 100-hour stress-rupture strength at 1600F was 15,000 psi. Excellent joints were produced by spot welding and localized induction heating. The oxidation resistance of unprotected 90 wt% tungsten compositions was not significantly affected by alloying."

The following document is a note describing the process of building a nuclear density gauge and its improved features in comparison to previously reported density gauges.

Introduction. As has been shown by Post, the total power required to produce a strong, steady-state magnetic field is strongly dependent upon the temperature at which the electrical conductor of the magnet operates. The power required for operation at very low temperature can, in some cases, be much less than that required for ambient temperature operation. The power required for low temperature operation depends on many system characteristics which include the metal chosen for the electrical conductor, the purity of this metal, and efficiency of the refrigeration equipment. This paper shows the relative power requirement, as a function of temperature, of a magnet with a particular shape and with a field strength of 100,000 gauss. Data is shown for three electrical conductors: copper, aluminum, and sodium.

Zircaloy-2 has a strong tendency to absorb oxygen and nitrogen at elevated temperatures. These gas impurities are extremely harmful, causing brittleness and loss of corrosion resistance. The production of ductile corrosion-resistant welds by present methods required shielding of the weld metal by an inert gas atmosphere or by a vacuum. The alternative to an inert gas atmosphere or a vacuum is reduction of the welding time to a few milliseconds of time to prevent gas absorption.

A study of the basic problems associated with the use of electrical propulsion systems for space travel has been carried out at the Lawrence Radiation Laboratory. The emphasis is on large systems capable of manned flight.

The purpose of the test was to determine the ability of the Control Air System to provide the necessary quantity and quality of clean, dry air to keep the rod drive mechanism stator and position indicator housings at about 3 PSIG in order to avoid low stator resistances resulting from condensation during plant cooldown. The Control Air System is capable of providing the quality of air specified in AEC letter SBO:JWF:100 dated November 17, 1958 of less than 44 grains of moisture per lb. of air in the control air line nearest the reactor chamber.